1.8.1.1.2 DCLL R&D Task Area Reports

Compiled by Neil Morley for the TBM Conference Call

Oct 6, 2005

Purpose of R&D in a project are to reduce risk

Risk that the experimental device will negatively impact ITER – plant safety, licensing– operation schedule

Risk that TBM experiments will not achieve experimental mission– Understanding of phenomena and modeling capability is

insufficient to interpret or utilize data– Failures in diagnostics or large inaccuracies in measurements

give incomplete or poor data– Unanticipated system performance leads to irrelevant or

unquantifiable operating conditions

Main DCLL R&D areas

1.8.1.1.2 R&D Morley

1.8.1.1.2.1 Tritium Permeation Merril

1.8.1.1.2.2 Thermofluid MHD Smolentsev

1.8.1.1.2.3 SiC/SiC Fab Process & Properties Katoh

1.8.1.1.2.4 SiC/PbLi/FS Compatibility Pint

1.8.1.1.2.5 FS Box Fabrication & Material Issues Rowcliffe,Kurtz

1.8.1.1.2.6 Helium Systems Subcomponent Tests Wong

1.8.1.1.2.7 PbLi Hydrogen Production Merril

1.8.1.1.2.8 Be Joining to FS Zinkle,Ulrickson

1.8.1.1.2.9 Virtual TBM Abdou

1.8.1.1.2.10 Advanced Diagnostics Morley

1.8.1.1.2.11 Integrated mockup tests Ulrickson,Tanaka

1.8.1.1.2.1 Tritium Permeation

Brad Merrill – INL

Potential Safety ExperimentsSupporting the US ITBM Program, cont.

Thermal Cycle Performance of He Pipe Permeation Barriers

• simulates thermal stress degradation of permeation barrier coatings for He pipes

• configuration matched to TBM design for coated components

• utilize tritium for barrier technology qualification

• external thermal cycles followed by testing in permeation rig for integrated effects

• thermal cycling in permeation rig for barrier dynamic response

Tritium Permeation Schedule

associated safety issues resolved

associated design issues resolved

WBS Label TitleQ3

Q4

Q1

Q2

Q3

Q4

Q1

Q2

Q3

Q4

Q1

Q2

Q3

Q4

Q1

Q2

Q3

Q4

Q1

Q2

Q3

Q4

Q1

Q2

Q3

Q4

Q1

Q2

Q3

Q4

1.8.1.1.2.1 Tritium Permeation1.8.1.1.2.1.1 Experiment design and definition1.8.1.1.2.1.2 Fabrication and testout1.8.1.1.2.1.3 Performance of experiments1.8.1.1.2.1.4 Input to detailed design1.8.1.1.2.1.5 Input to safety analysis

2005 2006 2007 2008 2009 2010 2011 2012

<-- ITER interface changes

• Test schedule set to provide input into the initial licensing process; but if the licensing procedure can be staged, then QA of barriers could be performed any time prior to DT operation

Out-of-pile Qualification Tests for Permeation Barriers

• Test cost estimated to be 2.8 $M over 4 years

• Total estimated cost is 2.8 $M over 4 years (15% experiment design, 25% experiment fabrication, 60 % performing experiments and data analysis)

1.8.1.1.2.2 Thermofluid MHD

Sergey Smolentsev - UCLA

Thermofluid MHD R&D This WBS includes research and development tasks and their associated

administration including experimental investigations, development of modeling tools, and performing numerical simulations to address the most critical aspects of Pb-17Li flows/heat transfer in the TBM under ITER DCLL conditions.The main purposes are:

– to provide specific information on MHD flows and heat transfer needed for the completion of the reference TBM design and its safety operation in ITER;

– to qualify and quantify the most critical MHD/heat transfer phenomena that can affect performance of the DCLL concept;

– to develop and validate needed thermofluid MHD modeling tools;– to access main MHD/heat transfer issues related to the Flow Channel Insert (SiCf/SiC and sandwich

FCIs) as a key element of the DCLL concept;– to provide other R&D WBS with the information they need to accomplish their goals;– as a preparation to tests in ITER, simulate conditions when the reference design can be used

for meaningful experiments, addressing the most important features of the higher performance regime;

– in cooperation with other level 6 WBS, to establish R&D plans and develop diagnostics tools for TBM tests in ITER.

IMPORTANT COMMENTS ON R&D and COSTING– All major R&D supporting the TBM design should be accomplished by the end of 2010.– From 2011 to 2015 we will concentrate on planning ITER tests with supporting experiments

and modeling, and will develop and integrate the Thermofluid MHD sub-module into the VTBM code.

– Almost all experiments will be supported with modeling. – When doing the R&D, we will specify special ITER tests to simulate basic features of the

higher performance regime, while keeping the exit Pb-17Li temperature at 470C. – We will reduce our R&D costs by using existing MHD facilities at UCLA and then projecting

the moderate (1-2 T) magnetic field results to the higher field region (~4 T) via engineering scaling and modeling.

– Some costs on modeling include SBIR.

Thermofluid MHD R&D Schedule

Subtask 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015

1. Modeling tools 3-D, complex geometry code Research codes Support of VTBM

2. FCI (normal operation) SiC FCI Sandwich FCI FCI Heat Transfer

3. FCI (transitions)

4. Pb-17Li Inlet Manifold

5. Heat Transfer Natural Convection 2-D Turbulence

6. Sub-module testing

7. Planning and Modeling ITER Tests Planning Modeling

- R&D to support reference design

- Development of modeling tools

- Planning tests in ITER with supporting experiments and modeling;

- Contribution to VTBM

Thermofluid MHD R&D Preliminary Cost Estimate

TOTAL COST FOR 10 YEARS, M$: 15.3

WBS # Task Name Duration, months

Cost, M

Task Description (WBS definition)

1.8.1.1.2.2.1 Modeling tools

120 10.0 This WBS includes development of predictive capability MHD software and their associated administration to address high Hartmann number MHD flows in the DCLL blanket. The efforts are towards the completion of a 3-D unstructured mesh parallel code, called HIMAG, and various 2-D and 3-D models and research codes aiming at particular problems that have a profound impact on blanket functionality, such as natural convection, 2-D turbulence, etc.

1.8.1.1.2.2.2 FCI (normal operation)

60 1.6 This WBS includes experiments and modeling and their associated administration to test FCI functionality and its performance as electric and thermal insulator in normal operation conditions. The experimental studies deploy different types of FCI to check effectiveness of the pressure equalization openings and the effect of overlap regions. The numerical studies are performed in 2-D first, and then in 3-D to address various 3-D flow effects, e.g. entry effects, effects of temperature on thermophysical properties, etc.

1.8.1.1.2.2.3 FCI (transitions)

24 0.7 This WBS includes experiments and their associated administration to qualify effects of transient events, associated with plasma disruptions, on the FCI by simulating eddy currents and pressure waves in the liquid metal during fast transitions of the applied magnetic field with a timescale of 10 1-102 ms.

1.8.1.1.2.2.4 Pb-17Li inlet manifold

24 0.7 This WBS includes experimental and modeling studies and their associated administration aiming at the design, testing and optimization of the inlet Pb-17Li manifold. The goal of the studies is to give recommendations for designing a manifold that provides uniform flow distribution through all its legs, without significant increase in the MHD pressure drop. The reduced scale manifolds will be tested in a moderate (1-2 T) magnetic field.

1.8.1.1.2.2.5 Heat transfer

36 1.1 This WBS includes experiments and modeling and their associated administration to study heat transfer phenomena associated with the effect of natural convection and 2-D turbulence in long poloidal blanket channels. The goal of the studies is to qualify the phenomena in terms of their effect on the blanket performance, to establish a database for effective transport coefficients needed for heat transfer calculations in higher performance regimes, and to validate the codes.

1.8.1.1.2.2.6 Sub-module testing

24 0.8 This WBS includes experimental tests of a reduced size sub-module and their associated administration. The sub-module consists of the inlet manifold and the poloidal ducts. The goal of testing is to address issues of the MHD pressure drop and flow balancing in normal and abnormal (such as cracked FCI) conditions.

1.8.1.1.2.2.7 Planning and modeling

ITER tests

48 0.4 This WBS includes planning thermofluid MHD tests in ITER along with supporting numerical simulations and their associated administration.

1.8.1.1.2.3 SiC/SiC FCI Fabrication and Properties

Yutai Katoh - ONRL

1.8.1.1.2.3 SiC/SiC FCI Fabrication and Properties

Task List and Descriptions1.8.1.1.2.3.1 Technical Planning  

  1.8.1.1.2.3.1.1   Recommendation on 0th-order SiC/SiC FCI fabrication Provide recommendation on materials for preliminary MHD experiment

  1.8.1.1.2.3.1.2   Initial analysis and reference strategy development Perform initial analysis of technical issues for SiC/SiC FCI

  1.8.1.1.2.3.1.3   Develop trans-electrical conduction measurement technique Establish electrical conductivity measurement in hot lab

  1.8.1.1.2.3.1.4   Develop test for stiffness matrix Establish test methods for mechanical properties including stiffness matrix

1.8.1.1.2.3.2 1st generation FCI SiC/SiC

  1.8.1.1.2.3.2.1   Insulating composite development Design and fabricate 1st round SiC/SiC FCI 

  1.8.1.1.2.3.2.2   Failure mode analysis Identify potential failure modes of SiC/SiC FCI

  1.8.1.1.2.3.2.3   Non-irradiated characterization Perform electrical/thermal/mechanical tests on 1st generation samples

  1.8.1.1.2.3.2.4   Material/architectural design refinement Provide feedback for 2nd round FCI SiC/SiC fabrication

1.8.1.1.2.3.3 Alternative Concept Plan, design, and perform small confirmative studies for alternative FCI concept.

  1.8.1.1.2.3.3.1   Reference strategy development Define initial strategy for alternative FCI  

1.8.1.1.2.3.4 2nd generation FCI SiC/SiC Production and testing of 2nd generation customized FCI SiC/SiC

  1.8.1.1.2.3.4.1   Material fabrication Fabricate material for FCI based on refined material / architectural design.

  1.8.1.1.2.3.4.2   Non-irradiated characterization Characterize non-irradiated physical and mechanical properties

  1.8.1.1.2.3.4.3   Model component fabrication Determine appropriate shaping technique and fabricate model components

  1.8.1.1.2.3.4.4   Analysis of FCI samples from flow channel experiment Perform analysis of samples taken from FCI in flow channel experiment.

1.8.1.1.2.3.5 Low Dose Irradiation Effects Determine effects of low dose irradiation of FCI properties and performance

  1.8.1.1.2.3.5.1   Differential swelling and creep Determine differential swelling and irradiation creep compliance

  1.8.1.1.2.3.5.2   Irradiated conductivities and baseline properties Determine irradiation effect on transport properties of SiC/SiC FCI

1.8.1.1.2.3 SiC/SiC FCI Fabrication and Properties

Task Schedule

1.8.1.1.2.3 Year

1 2 3 4 5 6 7 8 9 10

1.8.1.1.2.3.1 Technical Planning

1 Recommendation on 0th-order SiC/SiC FCI fabrication

2 Initial analysis and reference strategy development

3 Development of electrical conductivity measurement technique

4 Development of test method for stiffness matrix

1.8.1.1.2.3.2 1st Generation FCI SiC/SiC

1 Insulating composite development

2 Failure mode analysis

3 Non-irradiated characterization

4 Material/architectural design refinement1.8.1.1.2.3.3 Alternative Concept

1 Reference strategy development

1.8.1.1.2.3.4 2nd Generation or Alternate FCI SiC/SiC

1 Material fabrication

2 Non-irradiated characterization

3 Model component fabrication

4 Analysis of FCI samples from flow channel experiment1.8.1.1.2.3.5 Low Dose Irradiation Effect

1 Differential swelling and creep

2 Irradiated conductivities and baseline properties

SiC/SiC Fab Process & Properties

1.8.1.1.2.3 SiC/SiC FCI Fabrication and Properties

Costing Table

Schedule

WBS# Item # Activity ID Description QTY Units $/unit O/H Total $ HRS $/HR Total $

1.8.1.1.2.3.1 1 1 Oth-Order recommendation 40 180 72002 2 Reference Strategy Development 120 180 216003 3 Electrical conductivity test development 1 unit 80000 37152 117152 520 160 832004 4 Mechanical property test development 200 180 36000

1.8.1.1.2.3.2 1 5 Insulating composite development 2 unit 20000 18576 58576 200 180 360002 6 Failure mode analysis 320 160 512003 7 1st Generation Characterization 400 160 640004 8 Material design 400 180 72000

1.8.1.1.2.3.3 1 9 Alternative concept 400 180 720001.8.1.1.2.3.4 1 10 2nd Generation Fabrication 2 unit 21000 19505 61505 200 200 40000

2 11 2nd Generation Characterization 400 200 800003 12 Model component fabrication 1 total 80000 37152 117152 80 200 160004 13 Analysis of Flow Channel Experiment Samples 160 200 32000

1.8.1.1.2.3.5 1 14 Differential swelling and creep 4000 200 8000002 15 Irradiated conductivities and baseline properties 2400 200 480000

354385 $1,891,200

Note: 'Shipping/Tax' includes ORNL overhead.

Material/Equipment Labor

1.8.1.1.2.3 Total

1.8.1.1.2.4 SiC/PbLi/FS Compatibility

Bruce Pint - ONRL

SiC/PbLi/FS Compatibility Task Descriptions(Bruce Pint)

SiC/PbLi/FS Compatibility

This WBS includes research and development tasks required to establish the suitable compatibility of SiC based flow channel inserts with a flowing non-isothermal PbLi/FS system with maximum/minimum operation temperature 500/300C. This will require determination of maximum dissolution rates and any dissimilar material interactions/problems. The WBS is highly related to both 1.8.1.1.2.2 Thermofluid MHD ,1.8.1.1.2.3 SiC/SiC Fab Process & Properties as well as 1.8.1.3 PbLi Flow Loop research and design tasks.

1.8.1.1.2.4.1Review existing data on FS corrosion in PbLi, SiC corrosion in PbLi, impurity effects and any potential dissimilar metal problems based on thermodynamic data. Assess need for impurity control and susceptibility of weldments.

1.8.1.1.2.4.2The least data avialable is for dissimilar material effects. Therefore, screening capsule tests will be conducted to determine any possible interactions among SiC, FS and any other loop materials as well as any problems in weld areas.

1.8.1.1.2.4.3

If warranted by proceeding steps, conduct compatibility tests in thermal convection loop. This could be relatively inexpensive if it can be demonstrated that quartz is a suitable loop material. The most direct experiment is to include spceimens of SiC, SiC/SiC and FS in the hot and cold legs to determine dissimilar material effects.

1.8.1.1.2.4.4 Examination of specimens for wetting, weight loss, mass transfer and PbLi penetration.

1.8.1.1.2.4.5The LiPb loop being constructed as part of the Thermofluid MHD experiments could also be used for chemistry control and material compatiblity experiments. Support the loop design and construction in order to enable these compatibility testing missions.

1.8.1.1.2.4.6 If warranted by prior results, test second generation of materials.

1.8.1.1.2.4.7 Examination of specimens for wetting, weight loss, mass transfer and PbLi penetration.

1.8.1.1.2.4.8Examination of specimens taken from tested FCIs for wetting, mass transfer and PbLi penetration particularly noting the effect of magnetic field orientation and temperature.

Support PbLi flowloop design and fabrication

Testing of 2nd gen reference samplesAnalysis of 2nd gen reference sample

Analysis of FCI samples from mockup exp

Strategy planning and detailed data analysis

Capsule tests for dissimlar material effects

Testing of 1st gen reference samples

Analysis of 1st gen reference sample

1.8.1.1.2.4

1.8.1.1.2.5 FS Box Fabrication & Material Issues

Arthur Rowcliffe – Free agent

Rick Kurtz – PNL

FS Box Fabrication Tasks, Schedule, Effort

R&D TASKS – 1.8.1.1.2.5 TIME FRAME EFFORT per year

1. Utilize US-JAERI irradiation program to expand database on FM steels with emphasis on HIP-bonded and welded joints; establish relationships between as-fabricated hardness/microstructure and mechanical properties for neutron doses of 0.1dpa - 3.0 dpa at 300-500C.

Present – 2011 TBD

2. Determine unirradiated properties of prototypic joints and base metal produced by US or international vendors. Research results will be used to assess various fabrication methods and guide the selection process for Engineering & Design Task 1.8.1.1.3.1.

Present – 2009 1 FTE

3. Determine irradiation response of prototypic joints produced by US or international vendors.

2009 – 2011 TBD

4. Assess irradiation performance of FM steel/Be bonded joints (shared with Task 1.8.1.1.2.8)

2006 – 2009 TBD

1.8.1.1.2.6 Helium Systems Subcomponent Tests

Clement Wong - GA

1.8.1.1.2.6 Helium Systems Subcomponent Tests

This WBS includes the administration, R&D and subcomponents testing of helium systems in the TBM, specifically for the determination of FW heat transfer enhancement and module helium flow distributions.

1.8.1.1.2.6.1 Helium cooled first wall heat transfer enhancement

This WBS includes the administration and R&D to recommend the necessary first wall channel heat transfer enhancement design for the reference DCLL TBM design while satisfying all necessary design limits for all operation scenarios of the first test module, with consideration of efficient and cost effective design conversion to be applied to the integrated testing TBM. Both analytical and experimental work will be utilized. The experimental evaluation and demonstration of the heat transfer enhancement design will be performed with existing US facilities and/or with the DCLL mockup facility. If appropriate, international collaboration will be considered.

1.8.1.1.2.6.2 Helium cooled flow distribution

This WBS includes the administration and R&D to recommend the necessary helium flow channel design in order to satisfy the thermal-hydraulic performance of the DCLL TBM design with necessary uniform flow distribution and without the risk of flow instability for all operational phases of the first test module, and with consideration of efficient and cost effective design conversion to be applied to the integrated testing TBM. This WBS includes all components of the helium flow loops, including helium-cooled ferritic structure of the TBM, pipes and ancillary equipment. Design criteria will be established and both analytical and experimental work will be applied when appropriate. When analytical work cannot provide clear cut answers for the selected flow configuration, experimental investigation and demonstration will be applied to the problem area. Subsequent design recommendation will be made. The most likely areas that will need experimental demonstration are the flow plenum and distributions through all the coolant channels of the ferritic structure and first wall components. The experimental evaluation and demonstration of the flow distribution design will be performed with existing US helium flow loop facilities and/or with the DCLL mockup facility. If appropriate, international collaboration will be considered. The WBS will be closely coordinately with the engineering WBS 1.8.1.1.3

Helium Systems Subcomponent TestsSchedule

2005 2006 2007 2008 2009 2010 2011 2012

WBS #

1.8.1.1.2.6

1.8.1.1.2.6.1 He-cooled FW heat transfer enchancement

1 Adminstration2 Analysis

3 Test

1.8.1.1.2.6.2 He coolant flow distribution

1 Adminstration

2 Analysis

3 Test

Helium System subcomponents analysis and test

ITER Director appointed

Helium Systems Subcomponent R&D Preliminary Cost Estimate

1.8.1.1.2.7 PbLi/Water Hydrogen Production

Brad Merrill – INL

Potential Safety ExperimentsSupporting the US TBM Program

• simulates LOVA with pooling water and sprayed molten PbLi

• single and multiple droplet sizes or streamed injection

• variable surface area of exposed water

• gas analyzer measures moisture content and H2 generation

• view ports allow imaging of reaction surfaces, temperature measurements, and droplet dynamics

• The chemical reaction of primary concern for the DCLL TBM is the PbLi reaction with H2O

– ITER requires that the PbLi volume be limited to 0.28 m3 to ensure that the in-vessel H2 production is less than 2.5 kg

– Alternatively, a detailed analysis of PbLi/H2O reaction must be performed that considers a Pb-17Li spray into water (spray droplets that are ~ 2 mm in radius); this analysis is problematic because reaction rate data does not exist for such droplets

– Our DDD relied on data from a single test (pouring contact mode) that indicates that ~50% of the Li will react; however only the amount of H2 generated and the time to achieve this quantity of H2 were reported and very little additional information was given regarding important modeling phenomena such as Pb–17Li fragmentation, transient temperatures, and reaction rates at various conditions.

PbLi/H2O Hydrogen Production R&D Task

• Test schedule set to provide input into the initial licensing process, since this issue must be resolved before the TBM can be installed in ITER

• Common problem for DCLL and HCLL TBMs (collaboration may be possible)

PbLi/H2O Hydrogen Production R&D Task

• Total estimated cost is 2.4 $M over 4 years (25% experiment design, 23% experiment fabrication, 32 % performing experiments, 0% data analysis)

Be to FS Joining R&D1.8.1.1.2.8

October 6, 2005

M. UlricksonPresented on TBM R&D Call

Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company,for the United States Department of Energy’s National Nuclear Security Administration

under contract DE-AC04-94AL85000.

Be to FS Joining R&D R&D Tasks

1.8.1.1.2.8.1 Joining Research– Study interlayers (diffusion barriers) and joining techniques such as HIP or

brazing, mechanical tests (2 Phases) 1.8.1.1.2.8.3 TBM PFC Development

– Mockups of the TBM PFC will be fabricated for high heat flux testing. 20 by 100 mm (up to 1000 cycles) at 0.3-1.0 MW/m2, NDE and post test. (2 Phases)

1.8.1.1.2.8.5 Prototype PFC– A prototype TBM PFC for HHF testing ( full width and thickness but shorter). At

least 1000 (up to 10000 cycles) at 0.3 to 1.0 MW/m2. Pre and Post test examination.

1.8.1.1.2.8.6 Irradiation of TBM PFC– Measurement of the key properties of the Be to FS joints and joined (e.g.,

welded or HIPped) FS for irradiation to 2 dpa in HFIR. Testing of both irradiated and unirradiated samples will be done to compare the joints and measure reliability.

TBM PFC Development Schedule

Be to FS Joining R&D Cost Estimate

Task Cost Estimate (FY06$)

Joining Research $1220K

TBM PFC Development $2170K

Prototype TBM PFC Dev. $1000K

Irradiation Testing $314K

Virtual TBM Development1.8.1.1.2.9

Mohamed Abdou - UCLA

Virtual TBM Development TasksThis WBS includes the administration, development and testing of an integrated management tool software package aiming at the capability to simulate critically coupled physical phenomena including thermofluid MHD, thermalhydraulic, nuclear, thermomechanical, mass transfer, electromagnetic and structural aspects of the TBM system in ITER. Results of this integrated modeling package will be bench marked with ITER and other integrated testing results. The goal of this element is to provide predictive capability for TBM testing in ITER and advanced plasma burning devices.

Perform survey of existing code capabilities, their data needs and interfaces. Decide on best candidates for integration into VTBM master, and identify required data and data structure. Develop overarching strategy and flow plan for VTBM code

Establish primary executive routines, data structure, and user interface of VTBM code.

Integration of identified capabilities into the VTBM master code and validate

CAD/Thermofluid MHD/Thermalhydraulic/Neutronic

Beginning with CAD/Neutronics (currently under development) and integrating thermofluid/MHD and loop thermal hydraulics as the first stage. Required to estimate operating temperatures and pressures of all components of the TBM system. CAD interface all...

Structural ResponseInclude structural response to temperature and pressure loads including deformation and material stress.

Mass transferInclude additional models for mass (corrosion and tritium) transfer and transport in both the TBM and piping and ancillary systems.

Apply the evolving code to the problems related to the first and second TBMs

First TBM: mockups and ITER experiments

Apply evolving code to the simulation of mockup experiments and planned ITER TBM experiments for the first TBM. Attempt to benchmark code predictions against new data and make recommendations for design and operation of TBMs

2nd TBM: mockups and ITER experiments

Apply evolving code to the simulation of mockup experiments and planned ITER TBM experiments for the second TBM. Attempt to benchmark code predictions against new data and make recommendations for design and operation of TBMs

Code application

Integration of CapabilitiesExecutive routines and data structure

Strategy development and survey of simulation capabilities

Virtual TBM

Virtual TBM Development Tasks

1.5 man-yr/yr 2.5 man-yr/yr 1 man-yr/yr

Virtual TBM Development Preliminary Cost Estimate

Total labor as identified on previous page is ~19 man.year, or roughly a burdened cost of ~$5.5M.

Travel and computers, ~$0.3M Software costs, ~$0.3M

Total cost over 10 years: ~$6M

Advanced Diagnostics1.8.1.1.2.10

Neil Morley - UCLA

Advanced Diagnostics Tasks

Advanced Diagnostics

This WBS includes the research and development tasks and associated administration required to establish the final design and fabrication of specialized diagnostic systems needed in the 1st TBM in the ITER electromagnetic and plasma environment and for subsequent TBMs subject to the nuclear environment during the D-T phase of ITER.

1.8.1.1.2.10.1

This task is to monitor and participate at a low level in ITER programs developing diagnostics useful for the TBM including: activation foils and pneumatic deployment systems, activated water streams, microfission chambers, neutron spectrometers, IR surface temperature measurements, thermocouple temperature measurements, visual surface inspection, residual gas analysis, ragowsko coils, tritium flowrates. Nuclear analysis can be contributed as needed

1.8.1.1.2.10.2

This task is to monitor and participate at a low level diagnostic developments in the international community including IEA activities for nuclear measurements as well as adaptation of fission/fusion/neutron source diagnostics including techniques for measuring tritium production, nuclear heating, nuclear field, strain, pressure, flowrate, potential, load, etc. Nuclear analysiswill be performed as needed for perfomance verification

1.8.1.1.2.10.3Support of attachment and testing of first TBM diagnostics on mockups to be tested in prototypical temperature and heat flux tests

1.8.1.1.2.10.4

This R&D task is intended to quantify the nuclear field and measuremnet techniques in a TBM mockup. Various measuring techniques for neutron/ gamma fluxes, tritium production rate (TPR) and heating rate are compared among each other and to various calculation codes to verify their predictive capabilities prior to the fabrication of the 2nd TBM in ITER. Effect of insertion of tubes of various sizes on neutronics measurement will be investigated with sensitivity/uncertainty analysis and through direct calculation. Effect of leaving the measuring instruments for various length of time before retrieval will be studied to derive correction factors to be applied to the TBR placed in ITER. Opportunity for international collaboration will be investigated to use available 14 MeV neutron source (FNG, FNS).

Monitor ITER diagnostic developments

Monitor international diagnositc developments

Testing of nuclear diagnositics with in-pile mockups

Testing of first TBM diagnostics on mockups

1.8.1.1.2.10

Advanced Diagnostics Schedule

0.25 man.year/yr

0.5 man.year/yr

0.25 man.year/yr

0.5 man.year/yr

Preparation/operation of mockups included under integrated testing

In-pile testing in fusion neutron source relying on International collaboration

Advanced Diagnostics Preliminary Cost Estimate

Total labor as identified on previous page is ~6.75 man.year, or roughly a burdened cost of ~$1.9M over 10 years

Travel (largely international): ~$0.3M Mockups and mockup test facilities assumed to be

provided under integrated testing task Neutron sources assumed to be provided internationally Cost of test diagnostics: $0.5M

Total cost over 10 years: ~$2.7M (with some big assumptions)

TBM Integrated Testing

DCLL and HCCB ½ scale testsTina J. Tanaka

Task list, schedule and rough costsOctober 6, 2005

Integrated Testing Task list

He Loop– Specify, purchase, install and test a Helium hoop that is

adequate for testing both the DCLL and HCCB test blanket modules

Integrated test of ½ scale DCLL – Design and fabricate mockup, FW heating test with He cooling,

Overpressure test

Integrated test of ½ scale HCCB– Design and fabricate mockup, Flow test, overpressure test.

Integrated Testing Task schedule

Integrated Testing Rough Cost Breakdown

Task Cost

He loop $2,660K

DCLL test $1,680K

HCCB test $200K*

less $40K if DCLL is also done.

Cost Summary and Observation

R&D ~$41M

Tritium Permeation 2.8M

Thermofluid MHD 15.3M

SiC/SiC Fab Process & Properties 1.89M

SiC/PbLi/FS Compatibility 0

FS Box Fabrication & Material Issues 0

Helium Systems Subcomponent Tests .84M

PbLi Hydrogen Production 2.4M

Be Joining to FS (TBM PFC) 4.7M

Virtual TBM 6M

Advanced Diagnostics 2.7M

Integrated mockup tests 4.34M

Yearly average, ~$4M/yr

Weighting is towards middle 5 years

Still missing estimates for 2 subject areas –

2nd TBM mockups not included

WBS #

1.8.12005 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015

1.8.3.2 Interfaces and Design Integration

1.8.1.1.1 Administration

1.8.1.1.2 R&D

1 Tritium Permeation

2 Thermofluid MHD

3 SiC/SiC Fab Process & Properties

4 SiC/FS/PbLi Compatibility

5 FS Box Fabrication & Material Issues

6 Helium Systems Subcomponent Test

7 PbLi/H2O Hydrogen Production

8 Be joining to FS

9 Virtual DCLL TBM

10 Advanced Diagnostics

11 Integrated mockups, 1/4 to 1/2 scale

1.8.1.1.3 Engineering

Preliminary Design

Detailed Design

Title III Activities

1.8.1.1.4 TBM design and fabrication

Call for tender / Contract award

Manufacturing design (tooling & processing)

Material procurement

Fabrication

1.8.1.1.5 Assembly, Testing, and Installation

QA tests

Delivery to ITER site installation

DCLL Test Module ScheduleFirst plasmaITER Director appointed

final design

ITER Interface changes

baseline decisions

Schedule Summary

How to proceed?

Detailed discussions are necessary. I want to schedule a weekly call to discuss details of groups of related R&D and get a better concensus and level of detail

People who didn’t get to comment on this call should send detailed “chits” with concerns, questions, comments to the task leader, with cc to neil, clement, abdou.

I will continue to synthesize and talk to leaders individually to try to get a coherent plan and resource estimate by the end of October.

I will keep the evolving dictionary, schedule and cost at www.fusion.ucla.edu/ITER-TBM