inest ustc - american nuclear societycmpwg.ans.org/icrs12/presentations/yican wu cad- and...
TRANSCRIPT
INEST USTC
INEST USTC
Presented by Yican WU
Contributed by FDS Team
Institute of Nuclear Energy Safety Technology (INEST)
Chinese Academy of Sciences (CAS)
wwwfdsorgcn
mdashmdashmdashmdashmdashmdashmdashmdashmdashmdashmdashmdashmdashmdashmdash CMPWG amp ICRS Nara Sept 2~7 2012
CAD- and Image-based Modeling
for Monte Carlo Simulation in Radiation Protection and Radiotherapy
INEST USTC Institute of Nuclear Energy Safety Technology
Chinese Academy of Sciences (INEST CAS)
Originated from
ASIPP and USTC-SNST + new members
Founded on Sept28 2011
The major professionalfundamental research basis for nuclear energy safety technology
in China to promote the efficient and safe application of nuclear energy
Current Research Areas
1 Advanced Fission Reactor Design and RampD
(ADS reactor innovation concepts)
2 Fusion Hybrid Reactor Design and Nuclear
Technology RampD
(neutronics thermalhydraulics material tritium
blanket safety etc)
3 Basic Research on Nuclear Safety and
Nuclear Technology Applications
(theorymethodology materials software etc)
bull 15 Research Divisions
bull 5 Administration Departments
bull ~500 Staff + ~500 Students
Jointly sponsored by
bull Hefei Institutes of Physical Science CAS
(CASHIPS CAS)
bull University of Science and Technology of China
(USTC)
~350 Members FDS Team 2012
INEST USTC
Contents
I Introduction
II CAD-based Modeling
III Image-based Modeling
IV SuperMC simulation
V Mixed Visualization of Models amp Results
VI Summary
I Introduction
INEST USTC
Objectives of Accurate Radiotherapy Kill tumor cells to the utmost
Protect the normal tissues and the organs at risk to the great extent
External radiotherapy
The number of people dying of cancer each year
~7000000 in the world
~1500000 in China
If precision of the delivery of dose is improved by 1
Cure rate of early stage patients increases by 2
About 140000 patients will survive each year
The quality of radiotherapy is strongly related to the adopted dose modeling
methods (codes and models) in TPS (Treatment Planning System)
Radiation Treatment
INEST USTC
Ionizing and Non-Ionizing Radiation
A common phenomenon in our daily life
May do great harm to human body
Radiation Protection
Methods to evaluate organ dose
Experimental Measurement
Physical phantom
Crude simplified shape high cost
Limited usage in fact
Numerical Simulation
Computational phantom
Monte Carlo codes
Easy to evaluate organ dose
The accuracy of numerical simulation strongly depends on the adopted
modeling approach (codes and models)
dosimeter
INEST USTC
Modeling Needs for Various Application Purposes
Radiation protection
bullBuilding
bullRadiation facility (reactor accelerator etc)
bullHuman phantom
Radiation treatment
bullRadiation collimator
bullHuman phantom
Medical imaging
bullHuman phantom
CAD-based Modeling
(facilities building etc )
Image-based Modeling
(Stylized Voxeled BREP Phantom etc)
How to combine the CAD-based and Image-based models
for different applications
Human + Engineering System
INEST USTC
Modeling Needs for Various Types of Models
Stylized Phantoms Mathematical equations minimizing
computation time
Simplified shape
Voxel Phantoms More realistic representation of human
anatomy
Difficult to segment organs
BREP Phantoms NURBS and polygonal meshes
Easy to deform
Physical Phantom
Computational phantom
RANDO Phantom
VIP-MAN
RPI Pregnant Phantom
ORNL Phantom
How to easily update and improve the different
types of models
INEST USTC
Modeling Needs for Various Simulation Approaches
Monte Carlo Method (eg MCNP GEANT FLUKA TRIPOLI) bull Accurate
bull Time-consuming difficult for deep penetration
bull Manual geometry modeling
Deterministic numerical method (eg TORT) bull Good for deep penetration
bull Difficult for complex geometry ray-effects
Analytical method (eg FSPB) bull Fast
bull Inaccurate for inhomogeneous materials and zones
How to achieve automatic conversion among the models
for different simulation approaches codes
INEST USTC
Developed Radiation Programs
Integrated into Framework System Named VisualBUS
Highlights of Three Key Programs
Geometric and Physical Modeling Program MCAM
bull Automatic modeling for Monte Carlo and coupled codes
bull Coupling models of human facilities and building
Numerical Simulation of Neutronics
amp Radiation Transport Program SuperMC
bull Monte Carlo radiation transport
bull Coupling MCdeterministicanalytical methods
Model and Result Visualization Program RVIS
bull Rendering of geometry coupling physical property distributions
bull Virtual roaming and organic dose evaluation
Application to Radiotherapy Planning amp QA System ARTS
INEST USTC VisualBUS
CAD- amp Image-based Multi-Functional 4D NeutronicsRadiation Simulation System
Main Functions
CAD-basedImaged-based Modeling
bull Monte Carlo (MC) geometries
bull Discrete Ordinates (SN) geometries
bull MC-SN coupled geometries
bull CTMRIcolor photographs
4D Coupled Multi-Process Calculation
bull Radiation Transport
bull Isotope Burnup
bull Material Activation amp Irradiation Damage
bull Radiation Dose
bull Fuel management
Dynamical amp Visualized Analysis
bull Static dynamic physical data fields
bull Human virtual roaming amp dosimetry
assessment
Multi-objective Optimization
bull Artificially intelligent algorithms
bull Space optimization of irregular complex
solutions
bull Hybrid Evaluated Nuclear Data Library for fusionfission
hybrid systems
bull External functions for other physics process simulations such as
virtual assembly thermal-hydraulics safety environmental
impact estimate etc
CAD-based amp Image-based Modeling
Modeling for MC MCAM45 Modeling for Human MCAM6 Modeling for MC-SN Modeling for SN
FVAS Virtual Assembling
Neutronics-Thermohydraulics
Coupled Analysis
Magnetic-Thermohydraulics
Coupled Analysis
Extern
al F
un
ction
s
Dynamical amp Visualized Analysis
4D Coupled Calculation
GUI of calculation
GU
I of V
isu
alB
US
Fu
nctio
nal C
od
es
Field Visualization SVIP Virtual Roaming RVIS Dose Visualization MCAM6
II CAD-based Modeling
Introduction on
the program MCAM Version 4~5
Multi-Calculations Automatic Modeling
for Neutronics and Radiation Transport
bullVersion 4 for CAD-based MCNP and TORT modeling
bullVersion 5 extended for TRIPOLI GEANT4 FLUKA etc
bullVersion 6 extended for Image-based modeling
INEST USTC
Motivations
Monte Carlo (MC) particle transport simulation codes
(MCNP etc) are widely used for Computational Phantom
It is tedious error-prone and time-consuming
bull To prepare modify check upgrade models with geometry
and material information in manual text for those codes
bull To exchange and compare models quickly among various
existing codes of the state-of-the-art physical simulation
codes and CAD codes (AutoCAD CATIA etc)
Can these be done automatically by a program
INEST USTC
Objectives and Features
to develop an automatic modeling system for MC codes
named MCAM
Direct use of the existing CAD models
bull Support popular CAD formats
bull Automatic preprocessing for the CAD models
Easy preparation of the MC models
bull Geometry Description
bull Material Source Tally Description Cards
bull Miscellaneous Parameters
Visualization amp direct check of existing MC models amp results
bull 3D geometry visualization
bull Other information such as material and importance assignment
16
INEST USTC
mdashStarted in 1999 more than 100 man-years invested
History
MCAM 5 2008~
For TRIPOLI Geant4 FLUKA
MCAM 6 2008~
Imaged based modeling For MCNP and TORT
INEST USTC
Applications
bull Adopted as ITER reference code
bull Created the 3D ldquoITER reference
neutronics modelrdquo
bull Users gt 150 international
institutescompanies
ITER MCNP model Model in MCAM ITER CAD model
18
MCAM Version 40 Series Main Functions
Basic Functions
1 CAD MCNP Conversion
2 MCNP CAD Reverse Conversion
3 Model Simplifying amp Repairing
4 MCNP Model Analyzing amp Editing
5 CAD Geometry Model Creating
INEST USTC
MCAM Version 50 Series Main Functions
Basic Functions
bull Bi-directional conversion for various Monte Carlo
simulation codes TRIPOLI GEANT FLUKA etc
bullFree-form surface (eg Spline) processing
INEST USTC
Cells in
Group
Surface
Equations
Cell Properties
(MaterialImportance)
ITER MCNP Model GUI Example
INEST USTC
TORT input file
Extended SN Automatic Modeling
CAD SN（VisualBUS TORThellip）
Model in MCAM CAD model
INEST USTC
Extended MC-SN Coupled Automatic Modeling
bull Auto-modeling for MC-SN coupled
radiation transport simulation
bull Compatible with common CAD systems
Multi-directional conversion CAD MC amp SN models
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Presented by Yican WU
Contributed by FDS Team
Institute of Nuclear Energy Safety Technology (INEST)
Chinese Academy of Sciences (CAS)
wwwfdsorgcn
mdashmdashmdashmdashmdashmdashmdashmdashmdashmdashmdashmdashmdashmdashmdash CMPWG amp ICRS Nara Sept 2~7 2012
CAD- and Image-based Modeling
for Monte Carlo Simulation in Radiation Protection and Radiotherapy
INEST USTC Institute of Nuclear Energy Safety Technology
Chinese Academy of Sciences (INEST CAS)
Originated from
ASIPP and USTC-SNST + new members
Founded on Sept28 2011
The major professionalfundamental research basis for nuclear energy safety technology
in China to promote the efficient and safe application of nuclear energy
Current Research Areas
1 Advanced Fission Reactor Design and RampD
(ADS reactor innovation concepts)
2 Fusion Hybrid Reactor Design and Nuclear
Technology RampD
(neutronics thermalhydraulics material tritium
blanket safety etc)
3 Basic Research on Nuclear Safety and
Nuclear Technology Applications
(theorymethodology materials software etc)
bull 15 Research Divisions
bull 5 Administration Departments
bull ~500 Staff + ~500 Students
Jointly sponsored by
bull Hefei Institutes of Physical Science CAS
(CASHIPS CAS)
bull University of Science and Technology of China
(USTC)
~350 Members FDS Team 2012
INEST USTC
Contents
I Introduction
II CAD-based Modeling
III Image-based Modeling
IV SuperMC simulation
V Mixed Visualization of Models amp Results
VI Summary
I Introduction
INEST USTC
Objectives of Accurate Radiotherapy Kill tumor cells to the utmost
Protect the normal tissues and the organs at risk to the great extent
External radiotherapy
The number of people dying of cancer each year
~7000000 in the world
~1500000 in China
If precision of the delivery of dose is improved by 1
Cure rate of early stage patients increases by 2
About 140000 patients will survive each year
The quality of radiotherapy is strongly related to the adopted dose modeling
methods (codes and models) in TPS (Treatment Planning System)
Radiation Treatment
INEST USTC
Ionizing and Non-Ionizing Radiation
A common phenomenon in our daily life
May do great harm to human body
Radiation Protection
Methods to evaluate organ dose
Experimental Measurement
Physical phantom
Crude simplified shape high cost
Limited usage in fact
Numerical Simulation
Computational phantom
Monte Carlo codes
Easy to evaluate organ dose
The accuracy of numerical simulation strongly depends on the adopted
modeling approach (codes and models)
dosimeter
INEST USTC
Modeling Needs for Various Application Purposes
Radiation protection
bullBuilding
bullRadiation facility (reactor accelerator etc)
bullHuman phantom
Radiation treatment
bullRadiation collimator
bullHuman phantom
Medical imaging
bullHuman phantom
CAD-based Modeling
(facilities building etc )
Image-based Modeling
(Stylized Voxeled BREP Phantom etc)
How to combine the CAD-based and Image-based models
for different applications
Human + Engineering System
INEST USTC
Modeling Needs for Various Types of Models
Stylized Phantoms Mathematical equations minimizing
computation time
Simplified shape
Voxel Phantoms More realistic representation of human
anatomy
Difficult to segment organs
BREP Phantoms NURBS and polygonal meshes
Easy to deform
Physical Phantom
Computational phantom
RANDO Phantom
VIP-MAN
RPI Pregnant Phantom
ORNL Phantom
How to easily update and improve the different
types of models
INEST USTC
Modeling Needs for Various Simulation Approaches
Monte Carlo Method (eg MCNP GEANT FLUKA TRIPOLI) bull Accurate
bull Time-consuming difficult for deep penetration
bull Manual geometry modeling
Deterministic numerical method (eg TORT) bull Good for deep penetration
bull Difficult for complex geometry ray-effects
Analytical method (eg FSPB) bull Fast
bull Inaccurate for inhomogeneous materials and zones
How to achieve automatic conversion among the models
for different simulation approaches codes
INEST USTC
Developed Radiation Programs
Integrated into Framework System Named VisualBUS
Highlights of Three Key Programs
Geometric and Physical Modeling Program MCAM
bull Automatic modeling for Monte Carlo and coupled codes
bull Coupling models of human facilities and building
Numerical Simulation of Neutronics
amp Radiation Transport Program SuperMC
bull Monte Carlo radiation transport
bull Coupling MCdeterministicanalytical methods
Model and Result Visualization Program RVIS
bull Rendering of geometry coupling physical property distributions
bull Virtual roaming and organic dose evaluation
Application to Radiotherapy Planning amp QA System ARTS
INEST USTC VisualBUS
CAD- amp Image-based Multi-Functional 4D NeutronicsRadiation Simulation System
Main Functions
CAD-basedImaged-based Modeling
bull Monte Carlo (MC) geometries
bull Discrete Ordinates (SN) geometries
bull MC-SN coupled geometries
bull CTMRIcolor photographs
4D Coupled Multi-Process Calculation
bull Radiation Transport
bull Isotope Burnup
bull Material Activation amp Irradiation Damage
bull Radiation Dose
bull Fuel management
Dynamical amp Visualized Analysis
bull Static dynamic physical data fields
bull Human virtual roaming amp dosimetry
assessment
Multi-objective Optimization
bull Artificially intelligent algorithms
bull Space optimization of irregular complex
solutions
bull Hybrid Evaluated Nuclear Data Library for fusionfission
hybrid systems
bull External functions for other physics process simulations such as
virtual assembly thermal-hydraulics safety environmental
impact estimate etc
CAD-based amp Image-based Modeling
Modeling for MC MCAM45 Modeling for Human MCAM6 Modeling for MC-SN Modeling for SN
FVAS Virtual Assembling
Neutronics-Thermohydraulics
Coupled Analysis
Magnetic-Thermohydraulics
Coupled Analysis
Extern
al F
un
ction
s
Dynamical amp Visualized Analysis
4D Coupled Calculation
GUI of calculation
GU
I of V
isu
alB
US
Fu
nctio
nal C
od
es
Field Visualization SVIP Virtual Roaming RVIS Dose Visualization MCAM6
II CAD-based Modeling
Introduction on
the program MCAM Version 4~5
Multi-Calculations Automatic Modeling
for Neutronics and Radiation Transport
bullVersion 4 for CAD-based MCNP and TORT modeling
bullVersion 5 extended for TRIPOLI GEANT4 FLUKA etc
bullVersion 6 extended for Image-based modeling
INEST USTC
Motivations
Monte Carlo (MC) particle transport simulation codes
(MCNP etc) are widely used for Computational Phantom
It is tedious error-prone and time-consuming
bull To prepare modify check upgrade models with geometry
and material information in manual text for those codes
bull To exchange and compare models quickly among various
existing codes of the state-of-the-art physical simulation
codes and CAD codes (AutoCAD CATIA etc)
Can these be done automatically by a program
INEST USTC
Objectives and Features
to develop an automatic modeling system for MC codes
named MCAM
Direct use of the existing CAD models
bull Support popular CAD formats
bull Automatic preprocessing for the CAD models
Easy preparation of the MC models
bull Geometry Description
bull Material Source Tally Description Cards
bull Miscellaneous Parameters
Visualization amp direct check of existing MC models amp results
bull 3D geometry visualization
bull Other information such as material and importance assignment
16
INEST USTC
mdashStarted in 1999 more than 100 man-years invested
History
MCAM 5 2008~
For TRIPOLI Geant4 FLUKA
MCAM 6 2008~
Imaged based modeling For MCNP and TORT
INEST USTC
Applications
bull Adopted as ITER reference code
bull Created the 3D ldquoITER reference
neutronics modelrdquo
bull Users gt 150 international
institutescompanies
ITER MCNP model Model in MCAM ITER CAD model
18
MCAM Version 40 Series Main Functions
Basic Functions
1 CAD MCNP Conversion
2 MCNP CAD Reverse Conversion
3 Model Simplifying amp Repairing
4 MCNP Model Analyzing amp Editing
5 CAD Geometry Model Creating
INEST USTC
MCAM Version 50 Series Main Functions
Basic Functions
bull Bi-directional conversion for various Monte Carlo
simulation codes TRIPOLI GEANT FLUKA etc
bullFree-form surface (eg Spline) processing
INEST USTC
Cells in
Group
Surface
Equations
Cell Properties
(MaterialImportance)
ITER MCNP Model GUI Example
INEST USTC
TORT input file
Extended SN Automatic Modeling
CAD SN（VisualBUS TORThellip）
Model in MCAM CAD model
INEST USTC
Extended MC-SN Coupled Automatic Modeling
bull Auto-modeling for MC-SN coupled
radiation transport simulation
bull Compatible with common CAD systems
Multi-directional conversion CAD MC amp SN models
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC Institute of Nuclear Energy Safety Technology
Chinese Academy of Sciences (INEST CAS)
Originated from
ASIPP and USTC-SNST + new members
Founded on Sept28 2011
The major professionalfundamental research basis for nuclear energy safety technology
in China to promote the efficient and safe application of nuclear energy
Current Research Areas
1 Advanced Fission Reactor Design and RampD
(ADS reactor innovation concepts)
2 Fusion Hybrid Reactor Design and Nuclear
Technology RampD
(neutronics thermalhydraulics material tritium
blanket safety etc)
3 Basic Research on Nuclear Safety and
Nuclear Technology Applications
(theorymethodology materials software etc)
bull 15 Research Divisions
bull 5 Administration Departments
bull ~500 Staff + ~500 Students
Jointly sponsored by
bull Hefei Institutes of Physical Science CAS
(CASHIPS CAS)
bull University of Science and Technology of China
(USTC)
~350 Members FDS Team 2012
INEST USTC
Contents
I Introduction
II CAD-based Modeling
III Image-based Modeling
IV SuperMC simulation
V Mixed Visualization of Models amp Results
VI Summary
I Introduction
INEST USTC
Objectives of Accurate Radiotherapy Kill tumor cells to the utmost
Protect the normal tissues and the organs at risk to the great extent
External radiotherapy
The number of people dying of cancer each year
~7000000 in the world
~1500000 in China
If precision of the delivery of dose is improved by 1
Cure rate of early stage patients increases by 2
About 140000 patients will survive each year
The quality of radiotherapy is strongly related to the adopted dose modeling
methods (codes and models) in TPS (Treatment Planning System)
Radiation Treatment
INEST USTC
Ionizing and Non-Ionizing Radiation
A common phenomenon in our daily life
May do great harm to human body
Radiation Protection
Methods to evaluate organ dose
Experimental Measurement
Physical phantom
Crude simplified shape high cost
Limited usage in fact
Numerical Simulation
Computational phantom
Monte Carlo codes
Easy to evaluate organ dose
The accuracy of numerical simulation strongly depends on the adopted
modeling approach (codes and models)
dosimeter
INEST USTC
Modeling Needs for Various Application Purposes
Radiation protection
bullBuilding
bullRadiation facility (reactor accelerator etc)
bullHuman phantom
Radiation treatment
bullRadiation collimator
bullHuman phantom
Medical imaging
bullHuman phantom
CAD-based Modeling
(facilities building etc )
Image-based Modeling
(Stylized Voxeled BREP Phantom etc)
How to combine the CAD-based and Image-based models
for different applications
Human + Engineering System
INEST USTC
Modeling Needs for Various Types of Models
Stylized Phantoms Mathematical equations minimizing
computation time
Simplified shape
Voxel Phantoms More realistic representation of human
anatomy
Difficult to segment organs
BREP Phantoms NURBS and polygonal meshes
Easy to deform
Physical Phantom
Computational phantom
RANDO Phantom
VIP-MAN
RPI Pregnant Phantom
ORNL Phantom
How to easily update and improve the different
types of models
INEST USTC
Modeling Needs for Various Simulation Approaches
Monte Carlo Method (eg MCNP GEANT FLUKA TRIPOLI) bull Accurate
bull Time-consuming difficult for deep penetration
bull Manual geometry modeling
Deterministic numerical method (eg TORT) bull Good for deep penetration
bull Difficult for complex geometry ray-effects
Analytical method (eg FSPB) bull Fast
bull Inaccurate for inhomogeneous materials and zones
How to achieve automatic conversion among the models
for different simulation approaches codes
INEST USTC
Developed Radiation Programs
Integrated into Framework System Named VisualBUS
Highlights of Three Key Programs
Geometric and Physical Modeling Program MCAM
bull Automatic modeling for Monte Carlo and coupled codes
bull Coupling models of human facilities and building
Numerical Simulation of Neutronics
amp Radiation Transport Program SuperMC
bull Monte Carlo radiation transport
bull Coupling MCdeterministicanalytical methods
Model and Result Visualization Program RVIS
bull Rendering of geometry coupling physical property distributions
bull Virtual roaming and organic dose evaluation
Application to Radiotherapy Planning amp QA System ARTS
INEST USTC VisualBUS
CAD- amp Image-based Multi-Functional 4D NeutronicsRadiation Simulation System
Main Functions
CAD-basedImaged-based Modeling
bull Monte Carlo (MC) geometries
bull Discrete Ordinates (SN) geometries
bull MC-SN coupled geometries
bull CTMRIcolor photographs
4D Coupled Multi-Process Calculation
bull Radiation Transport
bull Isotope Burnup
bull Material Activation amp Irradiation Damage
bull Radiation Dose
bull Fuel management
Dynamical amp Visualized Analysis
bull Static dynamic physical data fields
bull Human virtual roaming amp dosimetry
assessment
Multi-objective Optimization
bull Artificially intelligent algorithms
bull Space optimization of irregular complex
solutions
bull Hybrid Evaluated Nuclear Data Library for fusionfission
hybrid systems
bull External functions for other physics process simulations such as
virtual assembly thermal-hydraulics safety environmental
impact estimate etc
CAD-based amp Image-based Modeling
Modeling for MC MCAM45 Modeling for Human MCAM6 Modeling for MC-SN Modeling for SN
FVAS Virtual Assembling
Neutronics-Thermohydraulics
Coupled Analysis
Magnetic-Thermohydraulics
Coupled Analysis
Extern
al F
un
ction
s
Dynamical amp Visualized Analysis
4D Coupled Calculation
GUI of calculation
GU
I of V
isu
alB
US
Fu
nctio
nal C
od
es
Field Visualization SVIP Virtual Roaming RVIS Dose Visualization MCAM6
II CAD-based Modeling
Introduction on
the program MCAM Version 4~5
Multi-Calculations Automatic Modeling
for Neutronics and Radiation Transport
bullVersion 4 for CAD-based MCNP and TORT modeling
bullVersion 5 extended for TRIPOLI GEANT4 FLUKA etc
bullVersion 6 extended for Image-based modeling
INEST USTC
Motivations
Monte Carlo (MC) particle transport simulation codes
(MCNP etc) are widely used for Computational Phantom
It is tedious error-prone and time-consuming
bull To prepare modify check upgrade models with geometry
and material information in manual text for those codes
bull To exchange and compare models quickly among various
existing codes of the state-of-the-art physical simulation
codes and CAD codes (AutoCAD CATIA etc)
Can these be done automatically by a program
INEST USTC
Objectives and Features
to develop an automatic modeling system for MC codes
named MCAM
Direct use of the existing CAD models
bull Support popular CAD formats
bull Automatic preprocessing for the CAD models
Easy preparation of the MC models
bull Geometry Description
bull Material Source Tally Description Cards
bull Miscellaneous Parameters
Visualization amp direct check of existing MC models amp results
bull 3D geometry visualization
bull Other information such as material and importance assignment
16
INEST USTC
mdashStarted in 1999 more than 100 man-years invested
History
MCAM 5 2008~
For TRIPOLI Geant4 FLUKA
MCAM 6 2008~
Imaged based modeling For MCNP and TORT
INEST USTC
Applications
bull Adopted as ITER reference code
bull Created the 3D ldquoITER reference
neutronics modelrdquo
bull Users gt 150 international
institutescompanies
ITER MCNP model Model in MCAM ITER CAD model
18
MCAM Version 40 Series Main Functions
Basic Functions
1 CAD MCNP Conversion
2 MCNP CAD Reverse Conversion
3 Model Simplifying amp Repairing
4 MCNP Model Analyzing amp Editing
5 CAD Geometry Model Creating
INEST USTC
MCAM Version 50 Series Main Functions
Basic Functions
bull Bi-directional conversion for various Monte Carlo
simulation codes TRIPOLI GEANT FLUKA etc
bullFree-form surface (eg Spline) processing
INEST USTC
Cells in
Group
Surface
Equations
Cell Properties
(MaterialImportance)
ITER MCNP Model GUI Example
INEST USTC
TORT input file
Extended SN Automatic Modeling
CAD SN（VisualBUS TORThellip）
Model in MCAM CAD model
INEST USTC
Extended MC-SN Coupled Automatic Modeling
bull Auto-modeling for MC-SN coupled
radiation transport simulation
bull Compatible with common CAD systems
Multi-directional conversion CAD MC amp SN models
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Contents
I Introduction
II CAD-based Modeling
III Image-based Modeling
IV SuperMC simulation
V Mixed Visualization of Models amp Results
VI Summary
I Introduction
INEST USTC
Objectives of Accurate Radiotherapy Kill tumor cells to the utmost
Protect the normal tissues and the organs at risk to the great extent
External radiotherapy
The number of people dying of cancer each year
~7000000 in the world
~1500000 in China
If precision of the delivery of dose is improved by 1
Cure rate of early stage patients increases by 2
About 140000 patients will survive each year
The quality of radiotherapy is strongly related to the adopted dose modeling
methods (codes and models) in TPS (Treatment Planning System)
Radiation Treatment
INEST USTC
Ionizing and Non-Ionizing Radiation
A common phenomenon in our daily life
May do great harm to human body
Radiation Protection
Methods to evaluate organ dose
Experimental Measurement
Physical phantom
Crude simplified shape high cost
Limited usage in fact
Numerical Simulation
Computational phantom
Monte Carlo codes
Easy to evaluate organ dose
The accuracy of numerical simulation strongly depends on the adopted
modeling approach (codes and models)
dosimeter
INEST USTC
Modeling Needs for Various Application Purposes
Radiation protection
bullBuilding
bullRadiation facility (reactor accelerator etc)
bullHuman phantom
Radiation treatment
bullRadiation collimator
bullHuman phantom
Medical imaging
bullHuman phantom
CAD-based Modeling
(facilities building etc )
Image-based Modeling
(Stylized Voxeled BREP Phantom etc)
How to combine the CAD-based and Image-based models
for different applications
Human + Engineering System
INEST USTC
Modeling Needs for Various Types of Models
Stylized Phantoms Mathematical equations minimizing
computation time
Simplified shape
Voxel Phantoms More realistic representation of human
anatomy
Difficult to segment organs
BREP Phantoms NURBS and polygonal meshes
Easy to deform
Physical Phantom
Computational phantom
RANDO Phantom
VIP-MAN
RPI Pregnant Phantom
ORNL Phantom
How to easily update and improve the different
types of models
INEST USTC
Modeling Needs for Various Simulation Approaches
Monte Carlo Method (eg MCNP GEANT FLUKA TRIPOLI) bull Accurate
bull Time-consuming difficult for deep penetration
bull Manual geometry modeling
Deterministic numerical method (eg TORT) bull Good for deep penetration
bull Difficult for complex geometry ray-effects
Analytical method (eg FSPB) bull Fast
bull Inaccurate for inhomogeneous materials and zones
How to achieve automatic conversion among the models
for different simulation approaches codes
INEST USTC
Developed Radiation Programs
Integrated into Framework System Named VisualBUS
Highlights of Three Key Programs
Geometric and Physical Modeling Program MCAM
bull Automatic modeling for Monte Carlo and coupled codes
bull Coupling models of human facilities and building
Numerical Simulation of Neutronics
amp Radiation Transport Program SuperMC
bull Monte Carlo radiation transport
bull Coupling MCdeterministicanalytical methods
Model and Result Visualization Program RVIS
bull Rendering of geometry coupling physical property distributions
bull Virtual roaming and organic dose evaluation
Application to Radiotherapy Planning amp QA System ARTS
INEST USTC VisualBUS
CAD- amp Image-based Multi-Functional 4D NeutronicsRadiation Simulation System
Main Functions
CAD-basedImaged-based Modeling
bull Monte Carlo (MC) geometries
bull Discrete Ordinates (SN) geometries
bull MC-SN coupled geometries
bull CTMRIcolor photographs
4D Coupled Multi-Process Calculation
bull Radiation Transport
bull Isotope Burnup
bull Material Activation amp Irradiation Damage
bull Radiation Dose
bull Fuel management
Dynamical amp Visualized Analysis
bull Static dynamic physical data fields
bull Human virtual roaming amp dosimetry
assessment
Multi-objective Optimization
bull Artificially intelligent algorithms
bull Space optimization of irregular complex
solutions
bull Hybrid Evaluated Nuclear Data Library for fusionfission
hybrid systems
bull External functions for other physics process simulations such as
virtual assembly thermal-hydraulics safety environmental
impact estimate etc
CAD-based amp Image-based Modeling
Modeling for MC MCAM45 Modeling for Human MCAM6 Modeling for MC-SN Modeling for SN
FVAS Virtual Assembling
Neutronics-Thermohydraulics
Coupled Analysis
Magnetic-Thermohydraulics
Coupled Analysis
Extern
al F
un
ction
s
Dynamical amp Visualized Analysis
4D Coupled Calculation
GUI of calculation
GU
I of V
isu
alB
US
Fu
nctio
nal C
od
es
Field Visualization SVIP Virtual Roaming RVIS Dose Visualization MCAM6
II CAD-based Modeling
Introduction on
the program MCAM Version 4~5
Multi-Calculations Automatic Modeling
for Neutronics and Radiation Transport
bullVersion 4 for CAD-based MCNP and TORT modeling
bullVersion 5 extended for TRIPOLI GEANT4 FLUKA etc
bullVersion 6 extended for Image-based modeling
INEST USTC
Motivations
Monte Carlo (MC) particle transport simulation codes
(MCNP etc) are widely used for Computational Phantom
It is tedious error-prone and time-consuming
bull To prepare modify check upgrade models with geometry
and material information in manual text for those codes
bull To exchange and compare models quickly among various
existing codes of the state-of-the-art physical simulation
codes and CAD codes (AutoCAD CATIA etc)
Can these be done automatically by a program
INEST USTC
Objectives and Features
to develop an automatic modeling system for MC codes
named MCAM
Direct use of the existing CAD models
bull Support popular CAD formats
bull Automatic preprocessing for the CAD models
Easy preparation of the MC models
bull Geometry Description
bull Material Source Tally Description Cards
bull Miscellaneous Parameters
Visualization amp direct check of existing MC models amp results
bull 3D geometry visualization
bull Other information such as material and importance assignment
16
INEST USTC
mdashStarted in 1999 more than 100 man-years invested
History
MCAM 5 2008~
For TRIPOLI Geant4 FLUKA
MCAM 6 2008~
Imaged based modeling For MCNP and TORT
INEST USTC
Applications
bull Adopted as ITER reference code
bull Created the 3D ldquoITER reference
neutronics modelrdquo
bull Users gt 150 international
institutescompanies
ITER MCNP model Model in MCAM ITER CAD model
18
MCAM Version 40 Series Main Functions
Basic Functions
1 CAD MCNP Conversion
2 MCNP CAD Reverse Conversion
3 Model Simplifying amp Repairing
4 MCNP Model Analyzing amp Editing
5 CAD Geometry Model Creating
INEST USTC
MCAM Version 50 Series Main Functions
Basic Functions
bull Bi-directional conversion for various Monte Carlo
simulation codes TRIPOLI GEANT FLUKA etc
bullFree-form surface (eg Spline) processing
INEST USTC
Cells in
Group
Surface
Equations
Cell Properties
(MaterialImportance)
ITER MCNP Model GUI Example
INEST USTC
TORT input file
Extended SN Automatic Modeling
CAD SN（VisualBUS TORThellip）
Model in MCAM CAD model
INEST USTC
Extended MC-SN Coupled Automatic Modeling
bull Auto-modeling for MC-SN coupled
radiation transport simulation
bull Compatible with common CAD systems
Multi-directional conversion CAD MC amp SN models
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
I Introduction
INEST USTC
Objectives of Accurate Radiotherapy Kill tumor cells to the utmost
Protect the normal tissues and the organs at risk to the great extent
External radiotherapy
The number of people dying of cancer each year
~7000000 in the world
~1500000 in China
If precision of the delivery of dose is improved by 1
Cure rate of early stage patients increases by 2
About 140000 patients will survive each year
The quality of radiotherapy is strongly related to the adopted dose modeling
methods (codes and models) in TPS (Treatment Planning System)
Radiation Treatment
INEST USTC
Ionizing and Non-Ionizing Radiation
A common phenomenon in our daily life
May do great harm to human body
Radiation Protection
Methods to evaluate organ dose
Experimental Measurement
Physical phantom
Crude simplified shape high cost
Limited usage in fact
Numerical Simulation
Computational phantom
Monte Carlo codes
Easy to evaluate organ dose
The accuracy of numerical simulation strongly depends on the adopted
modeling approach (codes and models)
dosimeter
INEST USTC
Modeling Needs for Various Application Purposes
Radiation protection
bullBuilding
bullRadiation facility (reactor accelerator etc)
bullHuman phantom
Radiation treatment
bullRadiation collimator
bullHuman phantom
Medical imaging
bullHuman phantom
CAD-based Modeling
(facilities building etc )
Image-based Modeling
(Stylized Voxeled BREP Phantom etc)
How to combine the CAD-based and Image-based models
for different applications
Human + Engineering System
INEST USTC
Modeling Needs for Various Types of Models
Stylized Phantoms Mathematical equations minimizing
computation time
Simplified shape
Voxel Phantoms More realistic representation of human
anatomy
Difficult to segment organs
BREP Phantoms NURBS and polygonal meshes
Easy to deform
Physical Phantom
Computational phantom
RANDO Phantom
VIP-MAN
RPI Pregnant Phantom
ORNL Phantom
How to easily update and improve the different
types of models
INEST USTC
Modeling Needs for Various Simulation Approaches
Monte Carlo Method (eg MCNP GEANT FLUKA TRIPOLI) bull Accurate
bull Time-consuming difficult for deep penetration
bull Manual geometry modeling
Deterministic numerical method (eg TORT) bull Good for deep penetration
bull Difficult for complex geometry ray-effects
Analytical method (eg FSPB) bull Fast
bull Inaccurate for inhomogeneous materials and zones
How to achieve automatic conversion among the models
for different simulation approaches codes
INEST USTC
Developed Radiation Programs
Integrated into Framework System Named VisualBUS
Highlights of Three Key Programs
Geometric and Physical Modeling Program MCAM
bull Automatic modeling for Monte Carlo and coupled codes
bull Coupling models of human facilities and building
Numerical Simulation of Neutronics
amp Radiation Transport Program SuperMC
bull Monte Carlo radiation transport
bull Coupling MCdeterministicanalytical methods
Model and Result Visualization Program RVIS
bull Rendering of geometry coupling physical property distributions
bull Virtual roaming and organic dose evaluation
Application to Radiotherapy Planning amp QA System ARTS
INEST USTC VisualBUS
CAD- amp Image-based Multi-Functional 4D NeutronicsRadiation Simulation System
Main Functions
CAD-basedImaged-based Modeling
bull Monte Carlo (MC) geometries
bull Discrete Ordinates (SN) geometries
bull MC-SN coupled geometries
bull CTMRIcolor photographs
4D Coupled Multi-Process Calculation
bull Radiation Transport
bull Isotope Burnup
bull Material Activation amp Irradiation Damage
bull Radiation Dose
bull Fuel management
Dynamical amp Visualized Analysis
bull Static dynamic physical data fields
bull Human virtual roaming amp dosimetry
assessment
Multi-objective Optimization
bull Artificially intelligent algorithms
bull Space optimization of irregular complex
solutions
bull Hybrid Evaluated Nuclear Data Library for fusionfission
hybrid systems
bull External functions for other physics process simulations such as
virtual assembly thermal-hydraulics safety environmental
impact estimate etc
CAD-based amp Image-based Modeling
Modeling for MC MCAM45 Modeling for Human MCAM6 Modeling for MC-SN Modeling for SN
FVAS Virtual Assembling
Neutronics-Thermohydraulics
Coupled Analysis
Magnetic-Thermohydraulics
Coupled Analysis
Extern
al F
un
ction
s
Dynamical amp Visualized Analysis
4D Coupled Calculation
GUI of calculation
GU
I of V
isu
alB
US
Fu
nctio
nal C
od
es
Field Visualization SVIP Virtual Roaming RVIS Dose Visualization MCAM6
II CAD-based Modeling
Introduction on
the program MCAM Version 4~5
Multi-Calculations Automatic Modeling
for Neutronics and Radiation Transport
bullVersion 4 for CAD-based MCNP and TORT modeling
bullVersion 5 extended for TRIPOLI GEANT4 FLUKA etc
bullVersion 6 extended for Image-based modeling
INEST USTC
Motivations
Monte Carlo (MC) particle transport simulation codes
(MCNP etc) are widely used for Computational Phantom
It is tedious error-prone and time-consuming
bull To prepare modify check upgrade models with geometry
and material information in manual text for those codes
bull To exchange and compare models quickly among various
existing codes of the state-of-the-art physical simulation
codes and CAD codes (AutoCAD CATIA etc)
Can these be done automatically by a program
INEST USTC
Objectives and Features
to develop an automatic modeling system for MC codes
named MCAM
Direct use of the existing CAD models
bull Support popular CAD formats
bull Automatic preprocessing for the CAD models
Easy preparation of the MC models
bull Geometry Description
bull Material Source Tally Description Cards
bull Miscellaneous Parameters
Visualization amp direct check of existing MC models amp results
bull 3D geometry visualization
bull Other information such as material and importance assignment
16
INEST USTC
mdashStarted in 1999 more than 100 man-years invested
History
MCAM 5 2008~
For TRIPOLI Geant4 FLUKA
MCAM 6 2008~
Imaged based modeling For MCNP and TORT
INEST USTC
Applications
bull Adopted as ITER reference code
bull Created the 3D ldquoITER reference
neutronics modelrdquo
bull Users gt 150 international
institutescompanies
ITER MCNP model Model in MCAM ITER CAD model
18
MCAM Version 40 Series Main Functions
Basic Functions
1 CAD MCNP Conversion
2 MCNP CAD Reverse Conversion
3 Model Simplifying amp Repairing
4 MCNP Model Analyzing amp Editing
5 CAD Geometry Model Creating
INEST USTC
MCAM Version 50 Series Main Functions
Basic Functions
bull Bi-directional conversion for various Monte Carlo
simulation codes TRIPOLI GEANT FLUKA etc
bullFree-form surface (eg Spline) processing
INEST USTC
Cells in
Group
Surface
Equations
Cell Properties
(MaterialImportance)
ITER MCNP Model GUI Example
INEST USTC
TORT input file
Extended SN Automatic Modeling
CAD SN（VisualBUS TORThellip）
Model in MCAM CAD model
INEST USTC
Extended MC-SN Coupled Automatic Modeling
bull Auto-modeling for MC-SN coupled
radiation transport simulation
bull Compatible with common CAD systems
Multi-directional conversion CAD MC amp SN models
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Objectives of Accurate Radiotherapy Kill tumor cells to the utmost
Protect the normal tissues and the organs at risk to the great extent
External radiotherapy
The number of people dying of cancer each year
~7000000 in the world
~1500000 in China
If precision of the delivery of dose is improved by 1
Cure rate of early stage patients increases by 2
About 140000 patients will survive each year
The quality of radiotherapy is strongly related to the adopted dose modeling
methods (codes and models) in TPS (Treatment Planning System)
Radiation Treatment
INEST USTC
Ionizing and Non-Ionizing Radiation
A common phenomenon in our daily life
May do great harm to human body
Radiation Protection
Methods to evaluate organ dose
Experimental Measurement
Physical phantom
Crude simplified shape high cost
Limited usage in fact
Numerical Simulation
Computational phantom
Monte Carlo codes
Easy to evaluate organ dose
The accuracy of numerical simulation strongly depends on the adopted
modeling approach (codes and models)
dosimeter
INEST USTC
Modeling Needs for Various Application Purposes
Radiation protection
bullBuilding
bullRadiation facility (reactor accelerator etc)
bullHuman phantom
Radiation treatment
bullRadiation collimator
bullHuman phantom
Medical imaging
bullHuman phantom
CAD-based Modeling
(facilities building etc )
Image-based Modeling
(Stylized Voxeled BREP Phantom etc)
How to combine the CAD-based and Image-based models
for different applications
Human + Engineering System
INEST USTC
Modeling Needs for Various Types of Models
Stylized Phantoms Mathematical equations minimizing
computation time
Simplified shape
Voxel Phantoms More realistic representation of human
anatomy
Difficult to segment organs
BREP Phantoms NURBS and polygonal meshes
Easy to deform
Physical Phantom
Computational phantom
RANDO Phantom
VIP-MAN
RPI Pregnant Phantom
ORNL Phantom
How to easily update and improve the different
types of models
INEST USTC
Modeling Needs for Various Simulation Approaches
Monte Carlo Method (eg MCNP GEANT FLUKA TRIPOLI) bull Accurate
bull Time-consuming difficult for deep penetration
bull Manual geometry modeling
Deterministic numerical method (eg TORT) bull Good for deep penetration
bull Difficult for complex geometry ray-effects
Analytical method (eg FSPB) bull Fast
bull Inaccurate for inhomogeneous materials and zones
How to achieve automatic conversion among the models
for different simulation approaches codes
INEST USTC
Developed Radiation Programs
Integrated into Framework System Named VisualBUS
Highlights of Three Key Programs
Geometric and Physical Modeling Program MCAM
bull Automatic modeling for Monte Carlo and coupled codes
bull Coupling models of human facilities and building
Numerical Simulation of Neutronics
amp Radiation Transport Program SuperMC
bull Monte Carlo radiation transport
bull Coupling MCdeterministicanalytical methods
Model and Result Visualization Program RVIS
bull Rendering of geometry coupling physical property distributions
bull Virtual roaming and organic dose evaluation
Application to Radiotherapy Planning amp QA System ARTS
INEST USTC VisualBUS
CAD- amp Image-based Multi-Functional 4D NeutronicsRadiation Simulation System
Main Functions
CAD-basedImaged-based Modeling
bull Monte Carlo (MC) geometries
bull Discrete Ordinates (SN) geometries
bull MC-SN coupled geometries
bull CTMRIcolor photographs
4D Coupled Multi-Process Calculation
bull Radiation Transport
bull Isotope Burnup
bull Material Activation amp Irradiation Damage
bull Radiation Dose
bull Fuel management
Dynamical amp Visualized Analysis
bull Static dynamic physical data fields
bull Human virtual roaming amp dosimetry
assessment
Multi-objective Optimization
bull Artificially intelligent algorithms
bull Space optimization of irregular complex
solutions
bull Hybrid Evaluated Nuclear Data Library for fusionfission
hybrid systems
bull External functions for other physics process simulations such as
virtual assembly thermal-hydraulics safety environmental
impact estimate etc
CAD-based amp Image-based Modeling
Modeling for MC MCAM45 Modeling for Human MCAM6 Modeling for MC-SN Modeling for SN
FVAS Virtual Assembling
Neutronics-Thermohydraulics
Coupled Analysis
Magnetic-Thermohydraulics
Coupled Analysis
Extern
al F
un
ction
s
Dynamical amp Visualized Analysis
4D Coupled Calculation
GUI of calculation
GU
I of V
isu
alB
US
Fu
nctio
nal C
od
es
Field Visualization SVIP Virtual Roaming RVIS Dose Visualization MCAM6
II CAD-based Modeling
Introduction on
the program MCAM Version 4~5
Multi-Calculations Automatic Modeling
for Neutronics and Radiation Transport
bullVersion 4 for CAD-based MCNP and TORT modeling
bullVersion 5 extended for TRIPOLI GEANT4 FLUKA etc
bullVersion 6 extended for Image-based modeling
INEST USTC
Motivations
Monte Carlo (MC) particle transport simulation codes
(MCNP etc) are widely used for Computational Phantom
It is tedious error-prone and time-consuming
bull To prepare modify check upgrade models with geometry
and material information in manual text for those codes
bull To exchange and compare models quickly among various
existing codes of the state-of-the-art physical simulation
codes and CAD codes (AutoCAD CATIA etc)
Can these be done automatically by a program
INEST USTC
Objectives and Features
to develop an automatic modeling system for MC codes
named MCAM
Direct use of the existing CAD models
bull Support popular CAD formats
bull Automatic preprocessing for the CAD models
Easy preparation of the MC models
bull Geometry Description
bull Material Source Tally Description Cards
bull Miscellaneous Parameters
Visualization amp direct check of existing MC models amp results
bull 3D geometry visualization
bull Other information such as material and importance assignment
16
INEST USTC
mdashStarted in 1999 more than 100 man-years invested
History
MCAM 5 2008~
For TRIPOLI Geant4 FLUKA
MCAM 6 2008~
Imaged based modeling For MCNP and TORT
INEST USTC
Applications
bull Adopted as ITER reference code
bull Created the 3D ldquoITER reference
neutronics modelrdquo
bull Users gt 150 international
institutescompanies
ITER MCNP model Model in MCAM ITER CAD model
18
MCAM Version 40 Series Main Functions
Basic Functions
1 CAD MCNP Conversion
2 MCNP CAD Reverse Conversion
3 Model Simplifying amp Repairing
4 MCNP Model Analyzing amp Editing
5 CAD Geometry Model Creating
INEST USTC
MCAM Version 50 Series Main Functions
Basic Functions
bull Bi-directional conversion for various Monte Carlo
simulation codes TRIPOLI GEANT FLUKA etc
bullFree-form surface (eg Spline) processing
INEST USTC
Cells in
Group
Surface
Equations
Cell Properties
(MaterialImportance)
ITER MCNP Model GUI Example
INEST USTC
TORT input file
Extended SN Automatic Modeling
CAD SN（VisualBUS TORThellip）
Model in MCAM CAD model
INEST USTC
Extended MC-SN Coupled Automatic Modeling
bull Auto-modeling for MC-SN coupled
radiation transport simulation
bull Compatible with common CAD systems
Multi-directional conversion CAD MC amp SN models
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Ionizing and Non-Ionizing Radiation
A common phenomenon in our daily life
May do great harm to human body
Radiation Protection
Methods to evaluate organ dose
Experimental Measurement
Physical phantom
Crude simplified shape high cost
Limited usage in fact
Numerical Simulation
Computational phantom
Monte Carlo codes
Easy to evaluate organ dose
The accuracy of numerical simulation strongly depends on the adopted
modeling approach (codes and models)
dosimeter
INEST USTC
Modeling Needs for Various Application Purposes
Radiation protection
bullBuilding
bullRadiation facility (reactor accelerator etc)
bullHuman phantom
Radiation treatment
bullRadiation collimator
bullHuman phantom
Medical imaging
bullHuman phantom
CAD-based Modeling
(facilities building etc )
Image-based Modeling
(Stylized Voxeled BREP Phantom etc)
How to combine the CAD-based and Image-based models
for different applications
Human + Engineering System
INEST USTC
Modeling Needs for Various Types of Models
Stylized Phantoms Mathematical equations minimizing
computation time
Simplified shape
Voxel Phantoms More realistic representation of human
anatomy
Difficult to segment organs
BREP Phantoms NURBS and polygonal meshes
Easy to deform
Physical Phantom
Computational phantom
RANDO Phantom
VIP-MAN
RPI Pregnant Phantom
ORNL Phantom
How to easily update and improve the different
types of models
INEST USTC
Modeling Needs for Various Simulation Approaches
Monte Carlo Method (eg MCNP GEANT FLUKA TRIPOLI) bull Accurate
bull Time-consuming difficult for deep penetration
bull Manual geometry modeling
Deterministic numerical method (eg TORT) bull Good for deep penetration
bull Difficult for complex geometry ray-effects
Analytical method (eg FSPB) bull Fast
bull Inaccurate for inhomogeneous materials and zones
How to achieve automatic conversion among the models
for different simulation approaches codes
INEST USTC
Developed Radiation Programs
Integrated into Framework System Named VisualBUS
Highlights of Three Key Programs
Geometric and Physical Modeling Program MCAM
bull Automatic modeling for Monte Carlo and coupled codes
bull Coupling models of human facilities and building
Numerical Simulation of Neutronics
amp Radiation Transport Program SuperMC
bull Monte Carlo radiation transport
bull Coupling MCdeterministicanalytical methods
Model and Result Visualization Program RVIS
bull Rendering of geometry coupling physical property distributions
bull Virtual roaming and organic dose evaluation
Application to Radiotherapy Planning amp QA System ARTS
INEST USTC VisualBUS
CAD- amp Image-based Multi-Functional 4D NeutronicsRadiation Simulation System
Main Functions
CAD-basedImaged-based Modeling
bull Monte Carlo (MC) geometries
bull Discrete Ordinates (SN) geometries
bull MC-SN coupled geometries
bull CTMRIcolor photographs
4D Coupled Multi-Process Calculation
bull Radiation Transport
bull Isotope Burnup
bull Material Activation amp Irradiation Damage
bull Radiation Dose
bull Fuel management
Dynamical amp Visualized Analysis
bull Static dynamic physical data fields
bull Human virtual roaming amp dosimetry
assessment
Multi-objective Optimization
bull Artificially intelligent algorithms
bull Space optimization of irregular complex
solutions
bull Hybrid Evaluated Nuclear Data Library for fusionfission
hybrid systems
bull External functions for other physics process simulations such as
virtual assembly thermal-hydraulics safety environmental
impact estimate etc
CAD-based amp Image-based Modeling
Modeling for MC MCAM45 Modeling for Human MCAM6 Modeling for MC-SN Modeling for SN
FVAS Virtual Assembling
Neutronics-Thermohydraulics
Coupled Analysis
Magnetic-Thermohydraulics
Coupled Analysis
Extern
al F
un
ction
s
Dynamical amp Visualized Analysis
4D Coupled Calculation
GUI of calculation
GU
I of V
isu
alB
US
Fu
nctio
nal C
od
es
Field Visualization SVIP Virtual Roaming RVIS Dose Visualization MCAM6
II CAD-based Modeling
Introduction on
the program MCAM Version 4~5
Multi-Calculations Automatic Modeling
for Neutronics and Radiation Transport
bullVersion 4 for CAD-based MCNP and TORT modeling
bullVersion 5 extended for TRIPOLI GEANT4 FLUKA etc
bullVersion 6 extended for Image-based modeling
INEST USTC
Motivations
Monte Carlo (MC) particle transport simulation codes
(MCNP etc) are widely used for Computational Phantom
It is tedious error-prone and time-consuming
bull To prepare modify check upgrade models with geometry
and material information in manual text for those codes
bull To exchange and compare models quickly among various
existing codes of the state-of-the-art physical simulation
codes and CAD codes (AutoCAD CATIA etc)
Can these be done automatically by a program
INEST USTC
Objectives and Features
to develop an automatic modeling system for MC codes
named MCAM
Direct use of the existing CAD models
bull Support popular CAD formats
bull Automatic preprocessing for the CAD models
Easy preparation of the MC models
bull Geometry Description
bull Material Source Tally Description Cards
bull Miscellaneous Parameters
Visualization amp direct check of existing MC models amp results
bull 3D geometry visualization
bull Other information such as material and importance assignment
16
INEST USTC
mdashStarted in 1999 more than 100 man-years invested
History
MCAM 5 2008~
For TRIPOLI Geant4 FLUKA
MCAM 6 2008~
Imaged based modeling For MCNP and TORT
INEST USTC
Applications
bull Adopted as ITER reference code
bull Created the 3D ldquoITER reference
neutronics modelrdquo
bull Users gt 150 international
institutescompanies
ITER MCNP model Model in MCAM ITER CAD model
18
MCAM Version 40 Series Main Functions
Basic Functions
1 CAD MCNP Conversion
2 MCNP CAD Reverse Conversion
3 Model Simplifying amp Repairing
4 MCNP Model Analyzing amp Editing
5 CAD Geometry Model Creating
INEST USTC
MCAM Version 50 Series Main Functions
Basic Functions
bull Bi-directional conversion for various Monte Carlo
simulation codes TRIPOLI GEANT FLUKA etc
bullFree-form surface (eg Spline) processing
INEST USTC
Cells in
Group
Surface
Equations
Cell Properties
(MaterialImportance)
ITER MCNP Model GUI Example
INEST USTC
TORT input file
Extended SN Automatic Modeling
CAD SN（VisualBUS TORThellip）
Model in MCAM CAD model
INEST USTC
Extended MC-SN Coupled Automatic Modeling
bull Auto-modeling for MC-SN coupled
radiation transport simulation
bull Compatible with common CAD systems
Multi-directional conversion CAD MC amp SN models
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Modeling Needs for Various Application Purposes
Radiation protection
bullBuilding
bullRadiation facility (reactor accelerator etc)
bullHuman phantom
Radiation treatment
bullRadiation collimator
bullHuman phantom
Medical imaging
bullHuman phantom
CAD-based Modeling
(facilities building etc )
Image-based Modeling
(Stylized Voxeled BREP Phantom etc)
How to combine the CAD-based and Image-based models
for different applications
Human + Engineering System
INEST USTC
Modeling Needs for Various Types of Models
Stylized Phantoms Mathematical equations minimizing
computation time
Simplified shape
Voxel Phantoms More realistic representation of human
anatomy
Difficult to segment organs
BREP Phantoms NURBS and polygonal meshes
Easy to deform
Physical Phantom
Computational phantom
RANDO Phantom
VIP-MAN
RPI Pregnant Phantom
ORNL Phantom
How to easily update and improve the different
types of models
INEST USTC
Modeling Needs for Various Simulation Approaches
Monte Carlo Method (eg MCNP GEANT FLUKA TRIPOLI) bull Accurate
bull Time-consuming difficult for deep penetration
bull Manual geometry modeling
Deterministic numerical method (eg TORT) bull Good for deep penetration
bull Difficult for complex geometry ray-effects
Analytical method (eg FSPB) bull Fast
bull Inaccurate for inhomogeneous materials and zones
How to achieve automatic conversion among the models
for different simulation approaches codes
INEST USTC
Developed Radiation Programs
Integrated into Framework System Named VisualBUS
Highlights of Three Key Programs
Geometric and Physical Modeling Program MCAM
bull Automatic modeling for Monte Carlo and coupled codes
bull Coupling models of human facilities and building
Numerical Simulation of Neutronics
amp Radiation Transport Program SuperMC
bull Monte Carlo radiation transport
bull Coupling MCdeterministicanalytical methods
Model and Result Visualization Program RVIS
bull Rendering of geometry coupling physical property distributions
bull Virtual roaming and organic dose evaluation
Application to Radiotherapy Planning amp QA System ARTS
INEST USTC VisualBUS
CAD- amp Image-based Multi-Functional 4D NeutronicsRadiation Simulation System
Main Functions
CAD-basedImaged-based Modeling
bull Monte Carlo (MC) geometries
bull Discrete Ordinates (SN) geometries
bull MC-SN coupled geometries
bull CTMRIcolor photographs
4D Coupled Multi-Process Calculation
bull Radiation Transport
bull Isotope Burnup
bull Material Activation amp Irradiation Damage
bull Radiation Dose
bull Fuel management
Dynamical amp Visualized Analysis
bull Static dynamic physical data fields
bull Human virtual roaming amp dosimetry
assessment
Multi-objective Optimization
bull Artificially intelligent algorithms
bull Space optimization of irregular complex
solutions
bull Hybrid Evaluated Nuclear Data Library for fusionfission
hybrid systems
bull External functions for other physics process simulations such as
virtual assembly thermal-hydraulics safety environmental
impact estimate etc
CAD-based amp Image-based Modeling
Modeling for MC MCAM45 Modeling for Human MCAM6 Modeling for MC-SN Modeling for SN
FVAS Virtual Assembling
Neutronics-Thermohydraulics
Coupled Analysis
Magnetic-Thermohydraulics
Coupled Analysis
Extern
al F
un
ction
s
Dynamical amp Visualized Analysis
4D Coupled Calculation
GUI of calculation
GU
I of V
isu
alB
US
Fu
nctio
nal C
od
es
Field Visualization SVIP Virtual Roaming RVIS Dose Visualization MCAM6
II CAD-based Modeling
Introduction on
the program MCAM Version 4~5
Multi-Calculations Automatic Modeling
for Neutronics and Radiation Transport
bullVersion 4 for CAD-based MCNP and TORT modeling
bullVersion 5 extended for TRIPOLI GEANT4 FLUKA etc
bullVersion 6 extended for Image-based modeling
INEST USTC
Motivations
Monte Carlo (MC) particle transport simulation codes
(MCNP etc) are widely used for Computational Phantom
It is tedious error-prone and time-consuming
bull To prepare modify check upgrade models with geometry
and material information in manual text for those codes
bull To exchange and compare models quickly among various
existing codes of the state-of-the-art physical simulation
codes and CAD codes (AutoCAD CATIA etc)
Can these be done automatically by a program
INEST USTC
Objectives and Features
to develop an automatic modeling system for MC codes
named MCAM
Direct use of the existing CAD models
bull Support popular CAD formats
bull Automatic preprocessing for the CAD models
Easy preparation of the MC models
bull Geometry Description
bull Material Source Tally Description Cards
bull Miscellaneous Parameters
Visualization amp direct check of existing MC models amp results
bull 3D geometry visualization
bull Other information such as material and importance assignment
16
INEST USTC
mdashStarted in 1999 more than 100 man-years invested
History
MCAM 5 2008~
For TRIPOLI Geant4 FLUKA
MCAM 6 2008~
Imaged based modeling For MCNP and TORT
INEST USTC
Applications
bull Adopted as ITER reference code
bull Created the 3D ldquoITER reference
neutronics modelrdquo
bull Users gt 150 international
institutescompanies
ITER MCNP model Model in MCAM ITER CAD model
18
MCAM Version 40 Series Main Functions
Basic Functions
1 CAD MCNP Conversion
2 MCNP CAD Reverse Conversion
3 Model Simplifying amp Repairing
4 MCNP Model Analyzing amp Editing
5 CAD Geometry Model Creating
INEST USTC
MCAM Version 50 Series Main Functions
Basic Functions
bull Bi-directional conversion for various Monte Carlo
simulation codes TRIPOLI GEANT FLUKA etc
bullFree-form surface (eg Spline) processing
INEST USTC
Cells in
Group
Surface
Equations
Cell Properties
(MaterialImportance)
ITER MCNP Model GUI Example
INEST USTC
TORT input file
Extended SN Automatic Modeling
CAD SN（VisualBUS TORThellip）
Model in MCAM CAD model
INEST USTC
Extended MC-SN Coupled Automatic Modeling
bull Auto-modeling for MC-SN coupled
radiation transport simulation
bull Compatible with common CAD systems
Multi-directional conversion CAD MC amp SN models
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Modeling Needs for Various Types of Models
Stylized Phantoms Mathematical equations minimizing
computation time
Simplified shape
Voxel Phantoms More realistic representation of human
anatomy
Difficult to segment organs
BREP Phantoms NURBS and polygonal meshes
Easy to deform
Physical Phantom
Computational phantom
RANDO Phantom
VIP-MAN
RPI Pregnant Phantom
ORNL Phantom
How to easily update and improve the different
types of models
INEST USTC
Modeling Needs for Various Simulation Approaches
Monte Carlo Method (eg MCNP GEANT FLUKA TRIPOLI) bull Accurate
bull Time-consuming difficult for deep penetration
bull Manual geometry modeling
Deterministic numerical method (eg TORT) bull Good for deep penetration
bull Difficult for complex geometry ray-effects
Analytical method (eg FSPB) bull Fast
bull Inaccurate for inhomogeneous materials and zones
How to achieve automatic conversion among the models
for different simulation approaches codes
INEST USTC
Developed Radiation Programs
Integrated into Framework System Named VisualBUS
Highlights of Three Key Programs
Geometric and Physical Modeling Program MCAM
bull Automatic modeling for Monte Carlo and coupled codes
bull Coupling models of human facilities and building
Numerical Simulation of Neutronics
amp Radiation Transport Program SuperMC
bull Monte Carlo radiation transport
bull Coupling MCdeterministicanalytical methods
Model and Result Visualization Program RVIS
bull Rendering of geometry coupling physical property distributions
bull Virtual roaming and organic dose evaluation
Application to Radiotherapy Planning amp QA System ARTS
INEST USTC VisualBUS
CAD- amp Image-based Multi-Functional 4D NeutronicsRadiation Simulation System
Main Functions
CAD-basedImaged-based Modeling
bull Monte Carlo (MC) geometries
bull Discrete Ordinates (SN) geometries
bull MC-SN coupled geometries
bull CTMRIcolor photographs
4D Coupled Multi-Process Calculation
bull Radiation Transport
bull Isotope Burnup
bull Material Activation amp Irradiation Damage
bull Radiation Dose
bull Fuel management
Dynamical amp Visualized Analysis
bull Static dynamic physical data fields
bull Human virtual roaming amp dosimetry
assessment
Multi-objective Optimization
bull Artificially intelligent algorithms
bull Space optimization of irregular complex
solutions
bull Hybrid Evaluated Nuclear Data Library for fusionfission
hybrid systems
bull External functions for other physics process simulations such as
virtual assembly thermal-hydraulics safety environmental
impact estimate etc
CAD-based amp Image-based Modeling
Modeling for MC MCAM45 Modeling for Human MCAM6 Modeling for MC-SN Modeling for SN
FVAS Virtual Assembling
Neutronics-Thermohydraulics
Coupled Analysis
Magnetic-Thermohydraulics
Coupled Analysis
Extern
al F
un
ction
s
Dynamical amp Visualized Analysis
4D Coupled Calculation
GUI of calculation
GU
I of V
isu
alB
US
Fu
nctio
nal C
od
es
Field Visualization SVIP Virtual Roaming RVIS Dose Visualization MCAM6
II CAD-based Modeling
Introduction on
the program MCAM Version 4~5
Multi-Calculations Automatic Modeling
for Neutronics and Radiation Transport
bullVersion 4 for CAD-based MCNP and TORT modeling
bullVersion 5 extended for TRIPOLI GEANT4 FLUKA etc
bullVersion 6 extended for Image-based modeling
INEST USTC
Motivations
Monte Carlo (MC) particle transport simulation codes
(MCNP etc) are widely used for Computational Phantom
It is tedious error-prone and time-consuming
bull To prepare modify check upgrade models with geometry
and material information in manual text for those codes
bull To exchange and compare models quickly among various
existing codes of the state-of-the-art physical simulation
codes and CAD codes (AutoCAD CATIA etc)
Can these be done automatically by a program
INEST USTC
Objectives and Features
to develop an automatic modeling system for MC codes
named MCAM
Direct use of the existing CAD models
bull Support popular CAD formats
bull Automatic preprocessing for the CAD models
Easy preparation of the MC models
bull Geometry Description
bull Material Source Tally Description Cards
bull Miscellaneous Parameters
Visualization amp direct check of existing MC models amp results
bull 3D geometry visualization
bull Other information such as material and importance assignment
16
INEST USTC
mdashStarted in 1999 more than 100 man-years invested
History
MCAM 5 2008~
For TRIPOLI Geant4 FLUKA
MCAM 6 2008~
Imaged based modeling For MCNP and TORT
INEST USTC
Applications
bull Adopted as ITER reference code
bull Created the 3D ldquoITER reference
neutronics modelrdquo
bull Users gt 150 international
institutescompanies
ITER MCNP model Model in MCAM ITER CAD model
18
MCAM Version 40 Series Main Functions
Basic Functions
1 CAD MCNP Conversion
2 MCNP CAD Reverse Conversion
3 Model Simplifying amp Repairing
4 MCNP Model Analyzing amp Editing
5 CAD Geometry Model Creating
INEST USTC
MCAM Version 50 Series Main Functions
Basic Functions
bull Bi-directional conversion for various Monte Carlo
simulation codes TRIPOLI GEANT FLUKA etc
bullFree-form surface (eg Spline) processing
INEST USTC
Cells in
Group
Surface
Equations
Cell Properties
(MaterialImportance)
ITER MCNP Model GUI Example
INEST USTC
TORT input file
Extended SN Automatic Modeling
CAD SN（VisualBUS TORThellip）
Model in MCAM CAD model
INEST USTC
Extended MC-SN Coupled Automatic Modeling
bull Auto-modeling for MC-SN coupled
radiation transport simulation
bull Compatible with common CAD systems
Multi-directional conversion CAD MC amp SN models
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Modeling Needs for Various Simulation Approaches
Monte Carlo Method (eg MCNP GEANT FLUKA TRIPOLI) bull Accurate
bull Time-consuming difficult for deep penetration
bull Manual geometry modeling
Deterministic numerical method (eg TORT) bull Good for deep penetration
bull Difficult for complex geometry ray-effects
Analytical method (eg FSPB) bull Fast
bull Inaccurate for inhomogeneous materials and zones
How to achieve automatic conversion among the models
for different simulation approaches codes
INEST USTC
Developed Radiation Programs
Integrated into Framework System Named VisualBUS
Highlights of Three Key Programs
Geometric and Physical Modeling Program MCAM
bull Automatic modeling for Monte Carlo and coupled codes
bull Coupling models of human facilities and building
Numerical Simulation of Neutronics
amp Radiation Transport Program SuperMC
bull Monte Carlo radiation transport
bull Coupling MCdeterministicanalytical methods
Model and Result Visualization Program RVIS
bull Rendering of geometry coupling physical property distributions
bull Virtual roaming and organic dose evaluation
Application to Radiotherapy Planning amp QA System ARTS
INEST USTC VisualBUS
CAD- amp Image-based Multi-Functional 4D NeutronicsRadiation Simulation System
Main Functions
CAD-basedImaged-based Modeling
bull Monte Carlo (MC) geometries
bull Discrete Ordinates (SN) geometries
bull MC-SN coupled geometries
bull CTMRIcolor photographs
4D Coupled Multi-Process Calculation
bull Radiation Transport
bull Isotope Burnup
bull Material Activation amp Irradiation Damage
bull Radiation Dose
bull Fuel management
Dynamical amp Visualized Analysis
bull Static dynamic physical data fields
bull Human virtual roaming amp dosimetry
assessment
Multi-objective Optimization
bull Artificially intelligent algorithms
bull Space optimization of irregular complex
solutions
bull Hybrid Evaluated Nuclear Data Library for fusionfission
hybrid systems
bull External functions for other physics process simulations such as
virtual assembly thermal-hydraulics safety environmental
impact estimate etc
CAD-based amp Image-based Modeling
Modeling for MC MCAM45 Modeling for Human MCAM6 Modeling for MC-SN Modeling for SN
FVAS Virtual Assembling
Neutronics-Thermohydraulics
Coupled Analysis
Magnetic-Thermohydraulics
Coupled Analysis
Extern
al F
un
ction
s
Dynamical amp Visualized Analysis
4D Coupled Calculation
GUI of calculation
GU
I of V
isu
alB
US
Fu
nctio
nal C
od
es
Field Visualization SVIP Virtual Roaming RVIS Dose Visualization MCAM6
II CAD-based Modeling
Introduction on
the program MCAM Version 4~5
Multi-Calculations Automatic Modeling
for Neutronics and Radiation Transport
bullVersion 4 for CAD-based MCNP and TORT modeling
bullVersion 5 extended for TRIPOLI GEANT4 FLUKA etc
bullVersion 6 extended for Image-based modeling
INEST USTC
Motivations
Monte Carlo (MC) particle transport simulation codes
(MCNP etc) are widely used for Computational Phantom
It is tedious error-prone and time-consuming
bull To prepare modify check upgrade models with geometry
and material information in manual text for those codes
bull To exchange and compare models quickly among various
existing codes of the state-of-the-art physical simulation
codes and CAD codes (AutoCAD CATIA etc)
Can these be done automatically by a program
INEST USTC
Objectives and Features
to develop an automatic modeling system for MC codes
named MCAM
Direct use of the existing CAD models
bull Support popular CAD formats
bull Automatic preprocessing for the CAD models
Easy preparation of the MC models
bull Geometry Description
bull Material Source Tally Description Cards
bull Miscellaneous Parameters
Visualization amp direct check of existing MC models amp results
bull 3D geometry visualization
bull Other information such as material and importance assignment
16
INEST USTC
mdashStarted in 1999 more than 100 man-years invested
History
MCAM 5 2008~
For TRIPOLI Geant4 FLUKA
MCAM 6 2008~
Imaged based modeling For MCNP and TORT
INEST USTC
Applications
bull Adopted as ITER reference code
bull Created the 3D ldquoITER reference
neutronics modelrdquo
bull Users gt 150 international
institutescompanies
ITER MCNP model Model in MCAM ITER CAD model
18
MCAM Version 40 Series Main Functions
Basic Functions
1 CAD MCNP Conversion
2 MCNP CAD Reverse Conversion
3 Model Simplifying amp Repairing
4 MCNP Model Analyzing amp Editing
5 CAD Geometry Model Creating
INEST USTC
MCAM Version 50 Series Main Functions
Basic Functions
bull Bi-directional conversion for various Monte Carlo
simulation codes TRIPOLI GEANT FLUKA etc
bullFree-form surface (eg Spline) processing
INEST USTC
Cells in
Group
Surface
Equations
Cell Properties
(MaterialImportance)
ITER MCNP Model GUI Example
INEST USTC
TORT input file
Extended SN Automatic Modeling
CAD SN（VisualBUS TORThellip）
Model in MCAM CAD model
INEST USTC
Extended MC-SN Coupled Automatic Modeling
bull Auto-modeling for MC-SN coupled
radiation transport simulation
bull Compatible with common CAD systems
Multi-directional conversion CAD MC amp SN models
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Developed Radiation Programs
Integrated into Framework System Named VisualBUS
Highlights of Three Key Programs
Geometric and Physical Modeling Program MCAM
bull Automatic modeling for Monte Carlo and coupled codes
bull Coupling models of human facilities and building
Numerical Simulation of Neutronics
amp Radiation Transport Program SuperMC
bull Monte Carlo radiation transport
bull Coupling MCdeterministicanalytical methods
Model and Result Visualization Program RVIS
bull Rendering of geometry coupling physical property distributions
bull Virtual roaming and organic dose evaluation
Application to Radiotherapy Planning amp QA System ARTS
INEST USTC VisualBUS
CAD- amp Image-based Multi-Functional 4D NeutronicsRadiation Simulation System
Main Functions
CAD-basedImaged-based Modeling
bull Monte Carlo (MC) geometries
bull Discrete Ordinates (SN) geometries
bull MC-SN coupled geometries
bull CTMRIcolor photographs
4D Coupled Multi-Process Calculation
bull Radiation Transport
bull Isotope Burnup
bull Material Activation amp Irradiation Damage
bull Radiation Dose
bull Fuel management
Dynamical amp Visualized Analysis
bull Static dynamic physical data fields
bull Human virtual roaming amp dosimetry
assessment
Multi-objective Optimization
bull Artificially intelligent algorithms
bull Space optimization of irregular complex
solutions
bull Hybrid Evaluated Nuclear Data Library for fusionfission
hybrid systems
bull External functions for other physics process simulations such as
virtual assembly thermal-hydraulics safety environmental
impact estimate etc
CAD-based amp Image-based Modeling
Modeling for MC MCAM45 Modeling for Human MCAM6 Modeling for MC-SN Modeling for SN
FVAS Virtual Assembling
Neutronics-Thermohydraulics
Coupled Analysis
Magnetic-Thermohydraulics
Coupled Analysis
Extern
al F
un
ction
s
Dynamical amp Visualized Analysis
4D Coupled Calculation
GUI of calculation
GU
I of V
isu
alB
US
Fu
nctio
nal C
od
es
Field Visualization SVIP Virtual Roaming RVIS Dose Visualization MCAM6
II CAD-based Modeling
Introduction on
the program MCAM Version 4~5
Multi-Calculations Automatic Modeling
for Neutronics and Radiation Transport
bullVersion 4 for CAD-based MCNP and TORT modeling
bullVersion 5 extended for TRIPOLI GEANT4 FLUKA etc
bullVersion 6 extended for Image-based modeling
INEST USTC
Motivations
Monte Carlo (MC) particle transport simulation codes
(MCNP etc) are widely used for Computational Phantom
It is tedious error-prone and time-consuming
bull To prepare modify check upgrade models with geometry
and material information in manual text for those codes
bull To exchange and compare models quickly among various
existing codes of the state-of-the-art physical simulation
codes and CAD codes (AutoCAD CATIA etc)
Can these be done automatically by a program
INEST USTC
Objectives and Features
to develop an automatic modeling system for MC codes
named MCAM
Direct use of the existing CAD models
bull Support popular CAD formats
bull Automatic preprocessing for the CAD models
Easy preparation of the MC models
bull Geometry Description
bull Material Source Tally Description Cards
bull Miscellaneous Parameters
Visualization amp direct check of existing MC models amp results
bull 3D geometry visualization
bull Other information such as material and importance assignment
16
INEST USTC
mdashStarted in 1999 more than 100 man-years invested
History
MCAM 5 2008~
For TRIPOLI Geant4 FLUKA
MCAM 6 2008~
Imaged based modeling For MCNP and TORT
INEST USTC
Applications
bull Adopted as ITER reference code
bull Created the 3D ldquoITER reference
neutronics modelrdquo
bull Users gt 150 international
institutescompanies
ITER MCNP model Model in MCAM ITER CAD model
18
MCAM Version 40 Series Main Functions
Basic Functions
1 CAD MCNP Conversion
2 MCNP CAD Reverse Conversion
3 Model Simplifying amp Repairing
4 MCNP Model Analyzing amp Editing
5 CAD Geometry Model Creating
INEST USTC
MCAM Version 50 Series Main Functions
Basic Functions
bull Bi-directional conversion for various Monte Carlo
simulation codes TRIPOLI GEANT FLUKA etc
bullFree-form surface (eg Spline) processing
INEST USTC
Cells in
Group
Surface
Equations
Cell Properties
(MaterialImportance)
ITER MCNP Model GUI Example
INEST USTC
TORT input file
Extended SN Automatic Modeling
CAD SN（VisualBUS TORThellip）
Model in MCAM CAD model
INEST USTC
Extended MC-SN Coupled Automatic Modeling
bull Auto-modeling for MC-SN coupled
radiation transport simulation
bull Compatible with common CAD systems
Multi-directional conversion CAD MC amp SN models
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC VisualBUS
CAD- amp Image-based Multi-Functional 4D NeutronicsRadiation Simulation System
Main Functions
CAD-basedImaged-based Modeling
bull Monte Carlo (MC) geometries
bull Discrete Ordinates (SN) geometries
bull MC-SN coupled geometries
bull CTMRIcolor photographs
4D Coupled Multi-Process Calculation
bull Radiation Transport
bull Isotope Burnup
bull Material Activation amp Irradiation Damage
bull Radiation Dose
bull Fuel management
Dynamical amp Visualized Analysis
bull Static dynamic physical data fields
bull Human virtual roaming amp dosimetry
assessment
Multi-objective Optimization
bull Artificially intelligent algorithms
bull Space optimization of irregular complex
solutions
bull Hybrid Evaluated Nuclear Data Library for fusionfission
hybrid systems
bull External functions for other physics process simulations such as
virtual assembly thermal-hydraulics safety environmental
impact estimate etc
CAD-based amp Image-based Modeling
Modeling for MC MCAM45 Modeling for Human MCAM6 Modeling for MC-SN Modeling for SN
FVAS Virtual Assembling
Neutronics-Thermohydraulics
Coupled Analysis
Magnetic-Thermohydraulics
Coupled Analysis
Extern
al F
un
ction
s
Dynamical amp Visualized Analysis
4D Coupled Calculation
GUI of calculation
GU
I of V
isu
alB
US
Fu
nctio
nal C
od
es
Field Visualization SVIP Virtual Roaming RVIS Dose Visualization MCAM6
II CAD-based Modeling
Introduction on
the program MCAM Version 4~5
Multi-Calculations Automatic Modeling
for Neutronics and Radiation Transport
bullVersion 4 for CAD-based MCNP and TORT modeling
bullVersion 5 extended for TRIPOLI GEANT4 FLUKA etc
bullVersion 6 extended for Image-based modeling
INEST USTC
Motivations
Monte Carlo (MC) particle transport simulation codes
(MCNP etc) are widely used for Computational Phantom
It is tedious error-prone and time-consuming
bull To prepare modify check upgrade models with geometry
and material information in manual text for those codes
bull To exchange and compare models quickly among various
existing codes of the state-of-the-art physical simulation
codes and CAD codes (AutoCAD CATIA etc)
Can these be done automatically by a program
INEST USTC
Objectives and Features
to develop an automatic modeling system for MC codes
named MCAM
Direct use of the existing CAD models
bull Support popular CAD formats
bull Automatic preprocessing for the CAD models
Easy preparation of the MC models
bull Geometry Description
bull Material Source Tally Description Cards
bull Miscellaneous Parameters
Visualization amp direct check of existing MC models amp results
bull 3D geometry visualization
bull Other information such as material and importance assignment
16
INEST USTC
mdashStarted in 1999 more than 100 man-years invested
History
MCAM 5 2008~
For TRIPOLI Geant4 FLUKA
MCAM 6 2008~
Imaged based modeling For MCNP and TORT
INEST USTC
Applications
bull Adopted as ITER reference code
bull Created the 3D ldquoITER reference
neutronics modelrdquo
bull Users gt 150 international
institutescompanies
ITER MCNP model Model in MCAM ITER CAD model
18
MCAM Version 40 Series Main Functions
Basic Functions
1 CAD MCNP Conversion
2 MCNP CAD Reverse Conversion
3 Model Simplifying amp Repairing
4 MCNP Model Analyzing amp Editing
5 CAD Geometry Model Creating
INEST USTC
MCAM Version 50 Series Main Functions
Basic Functions
bull Bi-directional conversion for various Monte Carlo
simulation codes TRIPOLI GEANT FLUKA etc
bullFree-form surface (eg Spline) processing
INEST USTC
Cells in
Group
Surface
Equations
Cell Properties
(MaterialImportance)
ITER MCNP Model GUI Example
INEST USTC
TORT input file
Extended SN Automatic Modeling
CAD SN（VisualBUS TORThellip）
Model in MCAM CAD model
INEST USTC
Extended MC-SN Coupled Automatic Modeling
bull Auto-modeling for MC-SN coupled
radiation transport simulation
bull Compatible with common CAD systems
Multi-directional conversion CAD MC amp SN models
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
CAD-based amp Image-based Modeling
Modeling for MC MCAM45 Modeling for Human MCAM6 Modeling for MC-SN Modeling for SN
FVAS Virtual Assembling
Neutronics-Thermohydraulics
Coupled Analysis
Magnetic-Thermohydraulics
Coupled Analysis
Extern
al F
un
ction
s
Dynamical amp Visualized Analysis
4D Coupled Calculation
GUI of calculation
GU
I of V
isu
alB
US
Fu
nctio
nal C
od
es
Field Visualization SVIP Virtual Roaming RVIS Dose Visualization MCAM6
II CAD-based Modeling
Introduction on
the program MCAM Version 4~5
Multi-Calculations Automatic Modeling
for Neutronics and Radiation Transport
bullVersion 4 for CAD-based MCNP and TORT modeling
bullVersion 5 extended for TRIPOLI GEANT4 FLUKA etc
bullVersion 6 extended for Image-based modeling
INEST USTC
Motivations
Monte Carlo (MC) particle transport simulation codes
(MCNP etc) are widely used for Computational Phantom
It is tedious error-prone and time-consuming
bull To prepare modify check upgrade models with geometry
and material information in manual text for those codes
bull To exchange and compare models quickly among various
existing codes of the state-of-the-art physical simulation
codes and CAD codes (AutoCAD CATIA etc)
Can these be done automatically by a program
INEST USTC
Objectives and Features
to develop an automatic modeling system for MC codes
named MCAM
Direct use of the existing CAD models
bull Support popular CAD formats
bull Automatic preprocessing for the CAD models
Easy preparation of the MC models
bull Geometry Description
bull Material Source Tally Description Cards
bull Miscellaneous Parameters
Visualization amp direct check of existing MC models amp results
bull 3D geometry visualization
bull Other information such as material and importance assignment
16
INEST USTC
mdashStarted in 1999 more than 100 man-years invested
History
MCAM 5 2008~
For TRIPOLI Geant4 FLUKA
MCAM 6 2008~
Imaged based modeling For MCNP and TORT
INEST USTC
Applications
bull Adopted as ITER reference code
bull Created the 3D ldquoITER reference
neutronics modelrdquo
bull Users gt 150 international
institutescompanies
ITER MCNP model Model in MCAM ITER CAD model
18
MCAM Version 40 Series Main Functions
Basic Functions
1 CAD MCNP Conversion
2 MCNP CAD Reverse Conversion
3 Model Simplifying amp Repairing
4 MCNP Model Analyzing amp Editing
5 CAD Geometry Model Creating
INEST USTC
MCAM Version 50 Series Main Functions
Basic Functions
bull Bi-directional conversion for various Monte Carlo
simulation codes TRIPOLI GEANT FLUKA etc
bullFree-form surface (eg Spline) processing
INEST USTC
Cells in
Group
Surface
Equations
Cell Properties
(MaterialImportance)
ITER MCNP Model GUI Example
INEST USTC
TORT input file
Extended SN Automatic Modeling
CAD SN（VisualBUS TORThellip）
Model in MCAM CAD model
INEST USTC
Extended MC-SN Coupled Automatic Modeling
bull Auto-modeling for MC-SN coupled
radiation transport simulation
bull Compatible with common CAD systems
Multi-directional conversion CAD MC amp SN models
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
II CAD-based Modeling
Introduction on
the program MCAM Version 4~5
Multi-Calculations Automatic Modeling
for Neutronics and Radiation Transport
bullVersion 4 for CAD-based MCNP and TORT modeling
bullVersion 5 extended for TRIPOLI GEANT4 FLUKA etc
bullVersion 6 extended for Image-based modeling
INEST USTC
Motivations
Monte Carlo (MC) particle transport simulation codes
(MCNP etc) are widely used for Computational Phantom
It is tedious error-prone and time-consuming
bull To prepare modify check upgrade models with geometry
and material information in manual text for those codes
bull To exchange and compare models quickly among various
existing codes of the state-of-the-art physical simulation
codes and CAD codes (AutoCAD CATIA etc)
Can these be done automatically by a program
INEST USTC
Objectives and Features
to develop an automatic modeling system for MC codes
named MCAM
Direct use of the existing CAD models
bull Support popular CAD formats
bull Automatic preprocessing for the CAD models
Easy preparation of the MC models
bull Geometry Description
bull Material Source Tally Description Cards
bull Miscellaneous Parameters
Visualization amp direct check of existing MC models amp results
bull 3D geometry visualization
bull Other information such as material and importance assignment
16
INEST USTC
mdashStarted in 1999 more than 100 man-years invested
History
MCAM 5 2008~
For TRIPOLI Geant4 FLUKA
MCAM 6 2008~
Imaged based modeling For MCNP and TORT
INEST USTC
Applications
bull Adopted as ITER reference code
bull Created the 3D ldquoITER reference
neutronics modelrdquo
bull Users gt 150 international
institutescompanies
ITER MCNP model Model in MCAM ITER CAD model
18
MCAM Version 40 Series Main Functions
Basic Functions
1 CAD MCNP Conversion
2 MCNP CAD Reverse Conversion
3 Model Simplifying amp Repairing
4 MCNP Model Analyzing amp Editing
5 CAD Geometry Model Creating
INEST USTC
MCAM Version 50 Series Main Functions
Basic Functions
bull Bi-directional conversion for various Monte Carlo
simulation codes TRIPOLI GEANT FLUKA etc
bullFree-form surface (eg Spline) processing
INEST USTC
Cells in
Group
Surface
Equations
Cell Properties
(MaterialImportance)
ITER MCNP Model GUI Example
INEST USTC
TORT input file
Extended SN Automatic Modeling
CAD SN（VisualBUS TORThellip）
Model in MCAM CAD model
INEST USTC
Extended MC-SN Coupled Automatic Modeling
bull Auto-modeling for MC-SN coupled
radiation transport simulation
bull Compatible with common CAD systems
Multi-directional conversion CAD MC amp SN models
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Motivations
Monte Carlo (MC) particle transport simulation codes
(MCNP etc) are widely used for Computational Phantom
It is tedious error-prone and time-consuming
bull To prepare modify check upgrade models with geometry
and material information in manual text for those codes
bull To exchange and compare models quickly among various
existing codes of the state-of-the-art physical simulation
codes and CAD codes (AutoCAD CATIA etc)
Can these be done automatically by a program
INEST USTC
Objectives and Features
to develop an automatic modeling system for MC codes
named MCAM
Direct use of the existing CAD models
bull Support popular CAD formats
bull Automatic preprocessing for the CAD models
Easy preparation of the MC models
bull Geometry Description
bull Material Source Tally Description Cards
bull Miscellaneous Parameters
Visualization amp direct check of existing MC models amp results
bull 3D geometry visualization
bull Other information such as material and importance assignment
16
INEST USTC
mdashStarted in 1999 more than 100 man-years invested
History
MCAM 5 2008~
For TRIPOLI Geant4 FLUKA
MCAM 6 2008~
Imaged based modeling For MCNP and TORT
INEST USTC
Applications
bull Adopted as ITER reference code
bull Created the 3D ldquoITER reference
neutronics modelrdquo
bull Users gt 150 international
institutescompanies
ITER MCNP model Model in MCAM ITER CAD model
18
MCAM Version 40 Series Main Functions
Basic Functions
1 CAD MCNP Conversion
2 MCNP CAD Reverse Conversion
3 Model Simplifying amp Repairing
4 MCNP Model Analyzing amp Editing
5 CAD Geometry Model Creating
INEST USTC
MCAM Version 50 Series Main Functions
Basic Functions
bull Bi-directional conversion for various Monte Carlo
simulation codes TRIPOLI GEANT FLUKA etc
bullFree-form surface (eg Spline) processing
INEST USTC
Cells in
Group
Surface
Equations
Cell Properties
(MaterialImportance)
ITER MCNP Model GUI Example
INEST USTC
TORT input file
Extended SN Automatic Modeling
CAD SN（VisualBUS TORThellip）
Model in MCAM CAD model
INEST USTC
Extended MC-SN Coupled Automatic Modeling
bull Auto-modeling for MC-SN coupled
radiation transport simulation
bull Compatible with common CAD systems
Multi-directional conversion CAD MC amp SN models
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Objectives and Features
to develop an automatic modeling system for MC codes
named MCAM
Direct use of the existing CAD models
bull Support popular CAD formats
bull Automatic preprocessing for the CAD models
Easy preparation of the MC models
bull Geometry Description
bull Material Source Tally Description Cards
bull Miscellaneous Parameters
Visualization amp direct check of existing MC models amp results
bull 3D geometry visualization
bull Other information such as material and importance assignment
16
INEST USTC
mdashStarted in 1999 more than 100 man-years invested
History
MCAM 5 2008~
For TRIPOLI Geant4 FLUKA
MCAM 6 2008~
Imaged based modeling For MCNP and TORT
INEST USTC
Applications
bull Adopted as ITER reference code
bull Created the 3D ldquoITER reference
neutronics modelrdquo
bull Users gt 150 international
institutescompanies
ITER MCNP model Model in MCAM ITER CAD model
18
MCAM Version 40 Series Main Functions
Basic Functions
1 CAD MCNP Conversion
2 MCNP CAD Reverse Conversion
3 Model Simplifying amp Repairing
4 MCNP Model Analyzing amp Editing
5 CAD Geometry Model Creating
INEST USTC
MCAM Version 50 Series Main Functions
Basic Functions
bull Bi-directional conversion for various Monte Carlo
simulation codes TRIPOLI GEANT FLUKA etc
bullFree-form surface (eg Spline) processing
INEST USTC
Cells in
Group
Surface
Equations
Cell Properties
(MaterialImportance)
ITER MCNP Model GUI Example
INEST USTC
TORT input file
Extended SN Automatic Modeling
CAD SN（VisualBUS TORThellip）
Model in MCAM CAD model
INEST USTC
Extended MC-SN Coupled Automatic Modeling
bull Auto-modeling for MC-SN coupled
radiation transport simulation
bull Compatible with common CAD systems
Multi-directional conversion CAD MC amp SN models
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
mdashStarted in 1999 more than 100 man-years invested
History
MCAM 5 2008~
For TRIPOLI Geant4 FLUKA
MCAM 6 2008~
Imaged based modeling For MCNP and TORT
INEST USTC
Applications
bull Adopted as ITER reference code
bull Created the 3D ldquoITER reference
neutronics modelrdquo
bull Users gt 150 international
institutescompanies
ITER MCNP model Model in MCAM ITER CAD model
18
MCAM Version 40 Series Main Functions
Basic Functions
1 CAD MCNP Conversion
2 MCNP CAD Reverse Conversion
3 Model Simplifying amp Repairing
4 MCNP Model Analyzing amp Editing
5 CAD Geometry Model Creating
INEST USTC
MCAM Version 50 Series Main Functions
Basic Functions
bull Bi-directional conversion for various Monte Carlo
simulation codes TRIPOLI GEANT FLUKA etc
bullFree-form surface (eg Spline) processing
INEST USTC
Cells in
Group
Surface
Equations
Cell Properties
(MaterialImportance)
ITER MCNP Model GUI Example
INEST USTC
TORT input file
Extended SN Automatic Modeling
CAD SN（VisualBUS TORThellip）
Model in MCAM CAD model
INEST USTC
Extended MC-SN Coupled Automatic Modeling
bull Auto-modeling for MC-SN coupled
radiation transport simulation
bull Compatible with common CAD systems
Multi-directional conversion CAD MC amp SN models
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Applications
bull Adopted as ITER reference code
bull Created the 3D ldquoITER reference
neutronics modelrdquo
bull Users gt 150 international
institutescompanies
ITER MCNP model Model in MCAM ITER CAD model
18
MCAM Version 40 Series Main Functions
Basic Functions
1 CAD MCNP Conversion
2 MCNP CAD Reverse Conversion
3 Model Simplifying amp Repairing
4 MCNP Model Analyzing amp Editing
5 CAD Geometry Model Creating
INEST USTC
MCAM Version 50 Series Main Functions
Basic Functions
bull Bi-directional conversion for various Monte Carlo
simulation codes TRIPOLI GEANT FLUKA etc
bullFree-form surface (eg Spline) processing
INEST USTC
Cells in
Group
Surface
Equations
Cell Properties
(MaterialImportance)
ITER MCNP Model GUI Example
INEST USTC
TORT input file
Extended SN Automatic Modeling
CAD SN（VisualBUS TORThellip）
Model in MCAM CAD model
INEST USTC
Extended MC-SN Coupled Automatic Modeling
bull Auto-modeling for MC-SN coupled
radiation transport simulation
bull Compatible with common CAD systems
Multi-directional conversion CAD MC amp SN models
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
MCAM Version 50 Series Main Functions
Basic Functions
bull Bi-directional conversion for various Monte Carlo
simulation codes TRIPOLI GEANT FLUKA etc
bullFree-form surface (eg Spline) processing
INEST USTC
Cells in
Group
Surface
Equations
Cell Properties
(MaterialImportance)
ITER MCNP Model GUI Example
INEST USTC
TORT input file
Extended SN Automatic Modeling
CAD SN（VisualBUS TORThellip）
Model in MCAM CAD model
INEST USTC
Extended MC-SN Coupled Automatic Modeling
bull Auto-modeling for MC-SN coupled
radiation transport simulation
bull Compatible with common CAD systems
Multi-directional conversion CAD MC amp SN models
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Cells in
Group
Surface
Equations
Cell Properties
(MaterialImportance)
ITER MCNP Model GUI Example
INEST USTC
TORT input file
Extended SN Automatic Modeling
CAD SN（VisualBUS TORThellip）
Model in MCAM CAD model
INEST USTC
Extended MC-SN Coupled Automatic Modeling
bull Auto-modeling for MC-SN coupled
radiation transport simulation
bull Compatible with common CAD systems
Multi-directional conversion CAD MC amp SN models
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
TORT input file
Extended SN Automatic Modeling
CAD SN（VisualBUS TORThellip）
Model in MCAM CAD model
INEST USTC
Extended MC-SN Coupled Automatic Modeling
bull Auto-modeling for MC-SN coupled
radiation transport simulation
bull Compatible with common CAD systems
Multi-directional conversion CAD MC amp SN models
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Extended MC-SN Coupled Automatic Modeling
bull Auto-modeling for MC-SN coupled
radiation transport simulation
bull Compatible with common CAD systems
Multi-directional conversion CAD MC amp SN models
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
Model Converting by MCAM for SN-code TORT
CAD model (Created by CATIA)
CAD Model reverted
from TORT input file
Convert with
SNAM
TORT input file
drawn by TRIPOLI
drawn by MCNP
CAD model reverted from
TRIPOLI input file
CAD model reverted from
MCNP input file
Convert with MCAM
TRIPOLI input file
MCNP input file
ITER
Benchmark
Process
Model Converting by MCAM for MCNP TRIPOLI TORT
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
ITER Benchmark Neutron Flux Results
Total neutron flux in Module 4
Code TRIPOLI MCNP VisualBUS (SN)
Neutron Source Uniform distribution in plasma chamber area
energy 1384MeVltElt1419MeV
Data Libraries FENDL21(MCNPVisualBUS) JEF2(TRIPOLI)
Tallis Neutron flux in the inboard blanket Module 4
(533ltZlt1538cm 10degltθlt20deg)
SN meshes 186times106 radial and vertical direction 2 cm per mesh
theta direction 5 degree per mesh
Results Max differences of total fluxes calculated by MCNP and
TORT are ~76 by MCNP and TRIPOLI are ~5 Radial flux distribution in Module 4
Module 4
Neutron flux
Radial range TORT MCNP TRIPOLI
result error result error
35935~370 1415E+12 1550E+12 216 1493E+12 273
37035~3815 4898E+12 4967E+12 112 4723E+12 145
3815~393 1905E+13 1828E+13 061 1785E+13 074
393~39735 4371E+13 4153E+13 050 4092E+13 063
39735~4045 7429E+13 6999E+13 035 6959E+13 040
360 370 380 390 400
1E12
1E13
Ne
utr
on
flu
x (
n(
sc
m2))
Radial distance (cm)
TORT
MCNP
TRIPOLI
Good Agreement
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
Inversion of VIP-Man MCNP Input to CAD model
MCAM Application Example at USA-RPI
3D View of VIP-Man 2D View of VIP-Man US-RPI Model G Xu et al
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
III Image-based Modeling
Introduction on
the program MCAM Version 6
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
MCAM Version 6 Series Main Functions
bullColor photographs
bullCT images
bullVoxel Model
bullBREP Model
bullMCNP Model
bullGEANT4 model
bullFLUKA model
bullTRIPOLI
bullTORT Model
bullSuperMC Model
bullFSPB Model
Basic Functions
bull medical Image-based modeling for human phantoms and models
conversion among various simulation codes
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Reconstruct model from medical images (CT)
Derive Material compositions and densities from CT
Medical images Voxels Cells MCNP input file
MCAM6 Image-based Modeling Method
CT images Voxel model
Merging voxels into cells
Air
Lung tissue
Muscle tissue
Cancellous bone
Adipose tissue
Cortical bone
( based on series CT images)
MCNP input file
Voxel-to-Cell
Combination and Size
Adjustment
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
MCAM6 Image-based Modeling Method
Segmented photo images Voxel model
Reconstruct model from segmented images(CTMRI Color photograph)
Derive Material compositions and densities from ICRP ICRU
Segmented Images Voxels MCNP input file
( based on series color photographs)
MCNP input file
Material
densities and
compositions
derived from
ICRP ICRU
Voxel-to-
Cell
Combinatio
n and Size
Adjustment
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Cells in
Group
Information window
(surface equationshellip)
Properties Pages
(Materialhellip)
MCAM 6 Human Phantom GUI
Example
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
FDS-HUMAN Phantom Original Dataset
from the Chinese Visible Human dataset
Color photograph
1 Total size of image 283GB
2 Format CRW -gt PNG
3 Number of slices 3641
4 Resolution 3072times2048
1 Total size of image 114Mb
2 Format Dicom
3 Number of slices 874
4 Resolution 512times512
CT
Dataset name CVH-2 the Chinese Visible Human dataset
Sex female Age 22y High 162cm Weight 54Kg
Provided by TMMU
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Organ Segmentation
46 organs ~20 persons 6 months
Locomotors System Skeleton Muscles Intervertebral disk Cartilage
Digestive system Esophagus Stomach Liver Gallbladder Pancreas Small intestine
Large intestine Salivary gland
Respiratory system Trachea Lung
Urogenital System Kidneys Ureter Mammary gland Urethra Uterus
Urinary bladder Vagina Ovary Uterine tube
Blood circulation Heart Artery Vein Red bone marrow
Nervous System Cerebellum Cerebral cortex Thalamus Cerebral medullary substance
Brain stem Spinal cord Optic nerve Optic chiasm
Endocrine system Thyroid gland Adrenal gland
Immune system Spleen Thymus
Additional Organs Eyeball Tongue Teeth Skin Pleural cavity Stomach content Cartilage
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
FDS-HUMAN Phantom 46 Sectioned Organs
FDS-HUMAN Computational Phantom
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
MCNP Model Derived from Color Photograph
(FDS-HUMAN Phantom)
2D View by MCAM Inversion 3D View by MCAM Inversion
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Dose Distribution Testing Calculation for ICRP Conversion Coefficients in Radiation Protection
Calculation model
FDS-HUMAN phantom based on color-photo
Photon Source
Direction AP PA LLAT RLAT ISO ROT
Energy 001 0015 002 003 004 005 006 008 01 015 02
03 04 05 06 08 1 15 2 3 4 5 6 8 10 MeV
Physical quantities
Organ absorbed dose (Dt) F8 tally
Kerma in air (Ka) F4 tally multiplied by flux to kerma factors
Dose conversion coefficient DtKa
ICRP (International Commission on Radiological Protection) 1996 Conversion coefficients for use in radiological
protection against external radiation ICRP Publication 74
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
01 1 10
00
02
04
06
08
10
12
14
16
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDSHuman(AP) FDSHuman(PA)
ICRP74(AP) ICRP74(PA)
Onoga(AP) Onago(PA)
JF(AP) JF(PA)
Lung
DtKa Dose Conversion Coefficients
01 1 10
00
02
04
06
08
10
12
14
16
18
Ab
so
rbe
d d
ose
Ka
(GyG
y)
Energy(MeV)
FDS-HUMAN(AP) FDS-HUMAN(PA)
ICRP74(AP) ICRP74(PA)
Onago(AP) Onago(PA)
JF(AP) JF(PA)
Stomach
The conversion coefficients of FDS-HUMAN agree
with the results of ICRP74 Onago and JF models
Antero-posterior (AP) direction
01 1 10
00
02
04
06
08
10
12
14
DtK
a(G
yG
y)
Energy(Mev)
FDSHuman(female)
Onago(female)
JF(female)
ICRP74
Thyroid
Posterior-antero (AP) direction
01 1 10
00
02
04
06
08
10
12
DtK
a(G
yG
y)
Energy
FDS-Human
Onago(female)
JF(female)
ICRP74
Thyroid
Right lateral (RLAT) direction
Left lateral (LLAT) direction
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
IV SuperMC
General Purposes Monte Carlo Simulation Program
for Neutronics and Radiation Transport
Directly coupled with MCAM and RVIS
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
bull Multi-Physical Computing
Multi-functional physical computing
Radiation transport isotopic burnup
material activation radiation damage
radiation dose biology damage
3D space and 1D time
MCSNMOC coupled method
Neutron photon electron proton ion etc
and coupled process among them
bull Automatic Modeling for Complex 3D Geometry MCAM
CAD Image based automatic modeling and
directly import of models
Support arbitrary 3D combination of solids
bull Process and Result Visualization RVIS
Visualized analysis of result data coupled with
geometries
Real-time particles tracking visualization
SuperMCSuper Monte Carlo Simulation Program
bull Acceleration Method
Rich variance reduction techniques
MPI and OpenMP mixed parallel
computing technology
Efficient parallel algorithm based on
particles space and data field
decomposition
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Development Route of SuperMC
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
V Geo-Phy Mixed Visualization
Introduction on
the program RVIS
Virtual Roaming Simulation and Organic Dose Assessment
in Nuclear Radiation Environment
Directly coupled with MCAM and SuperMC
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Virtual Roaming Simulation and Dose Assessment
Direct support of multi-codes
VisualBUS SuperMC MCNP TORT FISPACT ANISN
4D Visualized data analysis coupled with geometries
Virtual simulation of radiation environment for different scenarios
(maintenance decommission etc)
Dose assessment of human body or organs during operation etc
Mixed Rendering of 4D Data Fields and Geometries
Virtual Roaming Simulation and Organic Dose Evaluation
Dose Result Visualized Analysis Virtual Roaming
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Photon Flux Visualization by RVIS
MCNP Mesh Tally
Output File
Y cross-section
Z cross-section
X cross-section
--Based on MCNP Mesh Tally Output File
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Y cross-section
Z cross-section
X cross-section
Photon Flux Visualization by RVIS
MCNP Cell Tally
Output File
--Based on MCNP Cell Tally Output File
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Lung Front
Lateral Back
Photon Flux amp Anatomy Mixed Visualization by RVIS
ITER Simulation Video
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Virtual Roaming Simulation and Organic Dose Assessment
in Radiation Environment
bull Design Optimization
bull Operation Training
bull Maintenance Planning
bull Emergency Assessment
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
VI Summary
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Developed Programs
MCAM (modeling)
SuperMC (calculation)
RVIS (visualization)
Created Phantoms (FDS-HUMAN)
Accurate segmentation and process 46 segmented organs
High-precise computational phantoms
Automatic conversioncoupling among various-formated models
Color photograph images amp CT images-based models
Achieved Applications
Radiation protection (fusionfissionhybrid nuclear systems)
Radiotherapy
Integrated into the two software systems
VisualBUS and ARTS
Summary
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
INEST USTC
Radiation Group FDS Team Be experienced in using the state-of-the art radiation codes and
commercial CAD software systems MCNP TRIPOLI GEANTFLUKA
DOORS DANSYS FISPACT NJOY TRANSX
CATIA AutoCAD Solidwork UG Autodesk MDT
Be experienced in developing programs amp data libraries VisualBUS 4DS
MCAMSNAMRCAM
SuperMCAutoMOC
SVIPRVIS
HENDL
Be experienced in design amp analysis of advanced reactors and others
fusionfissionhybrid systems(FDSADS)
other radiation systems (eg radiotherapy) Radiation Group ~80 p
FDS
Team
~350 p
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn
Thanks for your attention
The End
Website wwwfdsorgcn
E-mail contactfdsorgcn