monaco/mavric: computational resources for radiation protection and shielding in scale douglas e....
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Monaco/MAVRIC: Computational Resources for Radiation Protection
and Shielding in SCALE Douglas E. Peplow, Stephen M. Bowman, James E. Horwedel, and John C. Wagner
Nuclear Science and Technology DivisionOak Ridge National Laboratory
Computational Resources for Radiation Protection and Shielding - IIAmerican Nuclear Society Winter Meeting
November 16, 2006 Albuquerque, New Mexico
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
Introduction
Monaco — multi-group Monte Carlo code MORSE physics SCALE Generalized Geometry Package (same as KenoVI)
MAVRIC — Automated Variance Reduction CADIS Methodology GTRUNCL3D and TORT Monaco for Monte Carlo Calculation
GeeWiz — the Windows GUI for using many SCALE programs
Monaco/MAVRIC will be part of SCALE 6
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
SCALE
Standardized Computer Analyses for Licensing Evaluation
Collection of codes for performing criticality safety radiation shielding spent fuel characterization reactor physcis radiation source terms and decay heat
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
SCALE
Functional modules – physics calculations KENO, Monaco, ORIGEN-S, NEWT, XSDRNPM
Control modules automate the execution and data exchange of individual codes to perform various types of analyses in calculation sequences CSAS, MAVRIC, TSUNAMI, TRITON
Multi-group and continuous energy cross-section data
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
Current SCALE Shielding Modules SAS1 – 1-D discrete ordinates Shielding Analysis Sequence
automates cross-section processing, transport calculation, and calculation of dose rates outside a defined shield
Combined 1-D criticality/shielding analysis (e.g. CAAS)
SAS4 – 3-D Monte Carlo Sheilding Analysis Sequence designed for calculation of radiation doses exterior to a transport/storage cask. Uses XSDRNPM to calculate adjoint fluxes for the generation of biasing parameters
MORSE 3-D Monte Carlo functional module used in SAS4 Different geometry package than the SCALE Monte Carlo
criticality (KENO) codes Legacy code, geometry package has not been updated in >20
years
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
Current SCALE Monte Carlo Shielding
SAS4 – Shielding Analysis Sequence Automated 1-D axial or radial variance reduction Not updated in more than a decade
Design limitations based on cylindrical cask geometry Effective for cask mid-plane and top center doses Not well suited to cask corners or very
heterogeneous geometries Not effective for general purpose shielding
analyses Hence, need for modern Monte Carlo tool with
automated 3-D variance reduction (AVR) for general shielding applications
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
Monaco
3-D Multi-group Monte Carlo MORSE physics SCALE Generalized Geometry Package (same
as KenoVI)
Fixed source Variety of geometric shapes Can use a mesh-based source
Tallies Point detectors, region tallies, mesh tally Convolves fluxes with detector responses
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
Monaco
Variance Reduction Biased source energy distribution Source direction distribution Path length stretching Point detector tallies Weight windows by region and energy group
Advanced Variance Reduction Mesh/energy group based importance map Mesh/energy group based biased source
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Monaco Example: Ueki Experiment
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
Monaco Example: Ueki Experiment
Table 6. Comparison of two hour results
0.1
1
10
100
1000
0 10 20 30 40 50Thickness (cm)
Dos
e E
quiv
alen
t Rat
e (µ
Sv/h
r)Measured
Monaco
Figure 3. Two hour results comparison
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
Monaco Example: Ueki Experiment
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
MAVRIC
3-D Automated Variance Reduction
SCALE cross section processing
GTRUNCL3D and TORT Computes the adjoint flux for a given response
Monaco for Monte Carlo calculation Importance map (weight windows for splitting
and roulette) Biased source distribution
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
CADIS Methodology
From the adjoint flux Importance map for MC transport (weight windows
for splitting and roulette) Biased source distribution
Biased source and importance map work together (i.e., are consistent)
A. Haghighat and J. C. Wagner, “Monte Carlo Variance Reduction with Deterministic Importance Functions,” Progress in Nuclear Energy, 42(1), 25-53, (2003).
Consistent Adjoint Driven Importance Sampling
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
CADIS Methodology
Want to find:
Erq ,
source emission probability distribution function (pdf)
S total source strength
),( Era
absorption cross section
),( Ers scattering cross section
),( Erd
detector response function
typical problem:
),( Er
Or some detector response related to flux:
flux
E V
d dVdEErErR ,,
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
CADIS Methodology
If the adjoint flux for a given detector response is known:
Then the detector response is simply:
),( Er
E V
dVdEErErqSR ,,
Unfortunately, the exact adjoint flux may be just as difficult to determine as the forward flux.
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
CADIS Methodology
With an approximate adjoint flux for a given detector response:
),( Er
Total detector response is approximated as:
Biased source distribution found to be:
Sampled particles start with weights of:
E V
dVdEErErqSR ,,
SR
ErErqErq
),(),(),(ˆ
),(),(0 Er
SRErw
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
CADIS Methodology
Weight window target weight values:
),(),(
Er
SRErw
Weight window size: (c=upper/lower)
lwc
w
2
1
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
SCALE Sequence: MAVRIC
Cross sections Multi-group SCALE libraries Create adjoint and forward cross section sets
Find the approximate adjoint flux GRTUNCL3-D – first collision code (for pnt det) TORT – 3-D discreet ordinates transport code
Forward Monte Carlo - Monaco Uses mesh-based biased source Uses mesh-based importance map (weight windows)
Automate as much as possible
An implementation of the CADIS Methodology
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
SCALE Sequence: MAVRIC
Monaco with Automated Variance Reduction using Importance Calculations
SCALEDriverandMAVRIC
Input
ICE
Monaco
End
Optional: TORT adjoint cross sections
Optional: 3-D discrete ordinates calculation
3-D Monte Carlo
Resonance cross-section processing
BONAMI / NITAWL orBONAMI / CENTRM / PMC
TORT
GRTUNCL-3D Optional: first-collision source calculation
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
MAVRIC Example – Weight targets
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
MAVRIC Example - Source Biasing
0
0.05
0.1
0.15
0.2
0.25
0.3
0.35
0 2 4 6 8 10Energy (MeV)
Prob
abil
ity
per M
eV
True
Biased
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
MAVRIC Example Results
FOM FOMThickness Monaco MAVRIC speedup
(cm) (/sec) (/sec)0 2.35E+02 1.11E+03 55 5.66E+00 1.30E+02 2310 2.15E+00 7.13E+01 3315 9.12E-01 2.94E+01 3220 4.40E-01 2.38E+01 5425 2.60E-01 2.19E+01 8430 1.16E-01 1.70E+01 14735 6.90E-02 1.49E+01 21640 3.79E-02 9.52E+00 25145 1.41E-02 1.37E+01 96750 5.68E-03 1.15E+01 2027
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TFOM
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MAVRIC Cask Example
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
MAVRIC Cask Example
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
MAVRIC Cask Example
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
MAVRIC Cask Example
TORT Monaco
1142 1.50E-09 (2.92%) 4.52E-06 (39.90%)
70 121 1.49E-09 (0.23%) 4.91E-06 (4.05%)
time (min)
uncollided total
Neutron dose rate (rem/hr)
Speed up: 583
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MAVRIC Cask Array Example
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
MAVRIC Cask Array Example
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
MAVRIC Cask Array Example
TORT Monaco
1083 3.45E-09 (0.84%) 2.83E-05 (6.33%)
44 664 3.08E-09 (0.13%) 2.91E-05 (1.47%)
time (min)
uncollided total
Neutron dose rate (rem/hr)
Speed up: 28
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
MAVRIC Cask Array Example
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
GeeWiz
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
KENO3D
Powerful 3-D interactive visualization tool that displays KENO V.a or KENO-VI geometry models
Plot calculated results (e.g., fluxes and reaction rates) over geometry
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OAK RIDGE NATIONAL LABORATORYU. S. DEPARTMENT OF ENERGY
KENO3D
help top view, side view toggle wireframe toggle highlight edges orbit rotate pan zoom options axis legend simple cuts rebuild in window dockable toolbars
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Future Work
MAVRIC Sequence Automatic homogenization in importance map Refine standard set of TORT parameters Incorporate new Monaco tallies Optimizing mesh tallies
Monaco Modern F95 programming structures Modern, block/keyword input structure Output to separate (html) tables Larger variety of source descriptions Larger variety of tally options – multipliers, totals
Cross-Section Data ENDF/B-VI coupled multigroup library
Testing, Testing, then a bit more Testing
Discussion & Questions