Overview and Meeting Objectives US ITER-TBM Meeting

Transcription

1 Overview and Meeting Objectives US ITER-TBM Meeting Mohamed Abdou August 10-12, 2005 at INEL

2 Purpose of the Meeting: To initiate the next phase (Phase 2) of US ITER-TBM activities - Definition of Tasks and Schedule - Identifying Task Groups, Leaders, Members Initiate costing activities per Nardella s request

3 The US ITER-TBM Program has successfully completed Phase I of its activities during the past two years (October 2003-August 2005) Accomplishments of Phase I Completed a technical study that led to selection of US Blanket Concepts for testing in ITER 1) Dual coolant lead-lithium with helium-cooled ferritic structure (DCLL) concept -US lead role in collaboration with other parties 2) Helium-cooled ceramic breeder with ferritic steel (HCCB) concept - US will support EU and J and collaborate with other parties Joined TBWG and completed all US obligations US provided strong intellectual and technical leadership to TBWG activities Completed DDD report for US concepts and delivered to TBWG on time Strong contributions to investigating and defining interface issues with the ITER device Important contributions to developing TBWG framework for testing plan on ITER and the need for strong collaboration among the parties

4 Accomplishments of Phase I (cont d) Carried out conceptual designs of ITER test articles for the US concepts Identified key R&D issues and initiated modeling and experiments in several important areas Began exploratory discussions with other parties on possible bi-lateral and multi-lateral collaboration on ITER-TBM

5 US-ITER TBM Phase 2 activities will focus more on engineering and developing cost / schedule / deliverables plan Primary Activities 1. Continue to contribute to TBWG activities Active participation Encourage international collaboration 2. Continue and strengthen Modeling and Experiments (R&D) for key issues of US ITER-TBM (This is the larger part of our activities) 3. Define, design, and plan engineering tests (sub-component tests, mockups, etc.) 4. Carry out TBM Costing Activity Additional Activities A. Explore partnerships and task sharing with each of the ITER Parties B. Encourage TBWG to go through an exercise of how to coordinate all Parties TBM activities and have strong collaborations C. Work with DOE, ITER Project Office, and US Community to recognize, formalize, and organize the US ITER-TBM Program

6 ITER Operation ITER operational plan has been discussed up to now only for the first 10 years. It includes 1 year of integration on sub system level, 2.5 years of initial operation in hydrogen, brief DD phase and a long tritium phase. ITER is designed for ~30000 pulses. Average neutron flux in the tritium phase is >0.5 MW/m 2. Maximum neutron flux at the equatorial level is up to 0.8 MW/m 2 at 500 MW. Average fluence after 20 years of operation may reach 0.3MWa/m 2.

7 Example: DCLL TBM Testing Schedule in ITER (4 sequential test articles) ITER Year ITER Operation Phase Magnet testing & vacuum HH- First Plasma HH HH DD Low Duty DT Low Duty DT Low Duty DT High Duty DT High Duty DT High Duty DT Progressive ITER Testing Conditions Toroidal B field Vacuum Heat flux B Field Disruptions Small neutron flux NWL Full disruption energy Fluence Accumula -tion Electromagnetic/ Structural (EM/S) TBM Install RH System checkout Transient EM Loading on structure and FCIs FW heat flux loading ITER field perturbation LM-MHD tests Nuclear Field/ Tritium Prod. (NF/TP) TBM Finalize Design Nuclear field Tritium production Nuclear heating Structure and FW heating Thermofluid/ MHD (T/M) TBM Finalize Design Thermal and electrical insulation Tritium permeation Velocity profiles Integrated (I) TBM Finalize Design High temperature effects Tritium permeation/recovery Integrated function, reliability

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9 To be certain that test blanket modules are compatible with tokamak operation the test modules must be installed as early as possible before beginning DT operation. There are several issues which must be investigated at this stage: - operation of test modules and supplementary equipment in strong magnetic field, - forces, acting on test modules during disruptions, - sputtering of the bare steel surface of the test module s first wall and necessity of using a Beryllium protective layer, - interference of the test modules with plasma confinement, - thermal loads on the test module s first wall. Moreover, most TBMs will be made of a martensitic/ferritic steel. Their magnetization in the ITER field will generate error fields - small perturbations of the axial symmetry of the poloidal magnetic field. Even small error fields (~10-4 of toroidal field) can induce in the plasma locked (i.e. non-rotating) modes. Locked modes are not stabilized by plasma rotation. Magnetic islands grow, degrade fusion performance and lead to disruptions. The error field may influence confinement of fast particles and change heat load on the test modules themselves. There are also other sources of the error fields like TF or PF coil misalignment creating error fields of a similar amplitude, but probably with different phases. The ITER magnet system is designed to compensate for these error fields. However, estimates show that the amount of ferritic steel in the current design is so high that the amplitude of the error fields created by test modules is close to limits for compensation. Taking into account uncertainties in prediction of the total error field and in the tolerance of the ITER plasma to error fields ITER does not request to change the design of test modules to-day and to limit the amount of ferritic steel. However, if the experiments during the hydrogen phase show that the level of the error fields is unacceptable, test module designers must be ready to meet such a request.

10 Three of the ITER 14 standard ports are dedicated for test blanket modules (They are Port #16, #18 and #2) Port # 16: Helium-cooled Ceramic Breeder TBMs Port # 18: Helium-cooled Lithium Lead /Dual Function Lithium Lead TBMs Water-Cooled Ceramic Breeder TBM Port # 2: Dual-Cooled Lithium Lead /Dual Function Lithium Lead TBMs Li-Breeder TBMs Helium-Cooled Ceramic Breeder TBM

11 Port Each standard equatorial port has an opening m wide and 2.2 m high which accommodate the frame m wide and m high. The face of each TBM is to be recessed by 50 mm from the first wall of blanket modules to protect modules from interaction with plasma (Unit: mm)

12 Definitions of names for Frame Port plug = Frame + TBMs Frame=FW structure + Box structure + Backside shields Backside Shield Cut-view Vertical cross-section of Frame (at the center of flexible supports) Vertical Port Frame Opening space for TBM

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15 EU TBMs for ITER HCPB TBM HCLL TBM Orientation: horizontal (half ITER port) Dimensions (mm): 740 x 1270 x ~700 (to be updated according to ITER port frame design optimization) 18 breeder cells (203 x 222) mm 2 Max. He flow: ~1.8 kg/s Adapted DEMO He flow scheme Orientation: vertical (half ITER port) Dimensions (mm): 626 x 1838 x ~575 (assuming a frame wall thickness of: 140 mm external wall, 100 mm central wall; can be updated according to reference frame design) 24 breeder cells (180 x 214) mm 2 Max. He flow: ~1.7 kg/s Adapted DEMO He flow scheme

16 ITER TBM Principal Tasks & Organization starting August 2005 (US Project Office: Ned Sauthoff DOE: Gene Nardella) (Team Leader: M. Abdou) I. Test Plan, Strategy, and Interface with ITER (Abdou) A. TBWG (Abdou, Sze, Ulrickson, with support from TBM Team) Perform tasks required by TBWG, including definition of interface to the ITER device and coordination among the Parties B. Evolve Details of Tests in ITER (Morley (DCLL), Ying (HCCB), Leaders of Technical Tasks) (Testing objectives, test sequence, number of concurrent test articles, items to be measured, etc.) Always identify reasons/importance/ justification for all tests C. International Cooperation (Abdou, US-TBWG members, US-IEA Representatives) II. III. Deliverables: ITER Test Article(s) and Ancillary Equipment for DCLL (Wong) and HCCB (Ying) (& support from all technical groups) Task II is concerned with the deliverables to ITER A. Design and Analysis B. Cost R&D for DCLL (Morley) and HCCB (Ying) (& all TBM Team) This task focuses on the R&D necessary to fulfill the Strategy and Test Plan identified in Task I and ensure meeting the requirements and time schedule of the deliverables of Task II A. Identify, Prioritize and Perform R&D Experiments and Modeling B. Mockup Facilities and Tests (Leader??) C. Cost Definition of mockup testing and facilities and schedule Design of mockup facilities (new and/or upgrade, or use of facilities outside the US)

17 TBM Technical Sub-Groups Technical Groups are responsible for all technical aspects of the project (for both DCLL and HCCB), including (a) performing R&D experiments and modeling; (b) support design and analysis; (c) costing. (Please note that some choices are limited by availability of funding, and in other cases by the availability of people.) 1. Ferritic Steel Structure Engineering and Fabrication (Kurtz, Zinkle, Sharafat, Odette,???) 2. Thermofluid MHD (Smolentsev, Morley, Ni, Narula, Ying, Messadek, Burris, Sketchley) 3. SiC FCI Material Development (also include metallic sandwich insulation) (Katoh, Henager, Youngblood, Sharafat, Zinkle) 4. Compatibility of SiC/PbLi/FS System (Pint, Sze, Tortorelli, Zinkle) 5. Structural Design and Failure Mode Analysis (Sharafat, Ghoniem, Blanchard, Kurtz, Odette,???) (Other people needed but funding is an issue: Saurin Majumdar (ANL), Tim McGreevy (ORNL)) 6. Pebble Bed Thermomechanics (Calderoni, Ying, An, Abou-Sena, Sharafat, Katoh) 7. Neutronics (Sawan, Youssef, Zhang)

18 TBM Technical Sub-Groups (cont d) 8. Safety (Merrill, Petti, Reyes,???) 9. Tritium Extraction and Control Systems (including tritium selfsufficiency analysis) (Sze, Merrill, Willms, Causey, Sawan, Youssef, Ying, Guo) 10. Diagnostics/Instrumentation/Control (???, Morley, Ying) 11. TBM Interface with Plasma (Ulrickson) Joining of beryllium to ferritic steel (???) Electromagnetics analysis (Ulrickson, Ni, Narula, Sharafat) 12. Mechanical Design (leader?, Sviatoslavsky, Dagher, Fogarty) 13. Mockup Facilities (Definition, design, costing and schedule) (???) 14. Thermofluid Helium Analysis (Wong, Calderoni, Sviatoslavsky, Ulrickson, Baxi) 15. Virtual TBM: Integrated Computer Simulation Capability (???)

19 Costing Activities for US ITER-TBM (Cost / Schedule / Deliverables) We are initiating the cost activities following Nardella s guidelines Time Schedule: Mid-August (this meeting): Finalize plan and responsibilities for the Costing Activity December 15, 2005: Distribute a near-final report of the Costing Activity for comments by the team, DOE, ITER Project Office, VLT, and others February 1, 2006: Submit Costing Activity Report to DOE ORGANIZATION of the Cost Activity: (Costing responsibilities are assigned to the leaders of principal tasks) Cost of R&D for DCLL (Morley) and for HCCB (Ying) Cost of Mockup Facilities (TBD??) Cost of the Test Articles (and ancillary equipment) to be delivered to ITER for DCLL (Wong) and for HCCB (Ying)

20 Framework for the US ITER-TBM Costing Activities Develop the Costs (cost/schedule/deliverables) for one scenario: - Good ITER utilization (Moderate Cost Scenario) - US lead on DCLL with strong collaboration with other parties - US support of EU, J on HCCB and collaboration with other parties The Deliverable is the First Test Article and ancillary equipment to be delivered to ITER on Day 1 The Cost is to be developed for the next 10-year period, i.e., all total costs until the delivery of the first test article(s) and ancillary equipment. Also need cost profiles. Some key points of the general approach: Start by agreeing on the FULL list of R&D required to deliver the ITER-TBMs Identify which R&D tasks are being done by other parties. The ones not being done by other Parties are then listed as POTENTIAL US Responsibility. Explore which of these tasks ( Potential US Responsibility ) can/should be negotiated with other ITER Partners for possible task/cost sharing We need to develop COST PROFILES, not just total cost (When do we start paying for mockup facilities and for fabricating the test articles? And at what rate? We are working on obtaining detailed cost estimates from EU and Japan and use them to calibrate our cost estimates (we have private data from 2 years ago) Identify the flexibility in US Strategy for ITER testing (temporal and spatial) that can accommodate different technical outcomes of R&D results and a range of available budgets

21 INFORMAL Guess and observations on the likely Costs The Cost of ITER-TBM Program consists of three parts: 1. Cost of R&D 2. Cost of Mockup Facilities 3. Cost of the Test Articles (and ancillary equipment) to be delivered to ITER Educated Guess (based on EU and Japanese informal estimates, prior exercises etc) Cost of R&D: $40M $60M total over 10 years ($4M $6M per year) Cost of Mockup Facilities: $10M $20M total over 3 5 years beginning a few years from now Cost of Construction of first Test Article to be delivered to ITER: $2M $3M total beginning in about 7 years Cost of Ancillary Equipment to be delivered to ITER: TBD (probably a few million beginning in about 8 years) The R&D cost will be the larger part of the total cost. But this R&D is actually the core of the base program anyway. ITER-TBM is the most important focus of Fusion Nuclear Technology over the next 30 years or so. Therefore, it should logically be the highest priority for the base program. Therefore, we expect most of the R&D can and should be covered by the base technology (but we have to examine of course whether current budgets for the base program are adequate). We need to prioritize the R&D, estimate the cost of the R&D over the next 10 years and compare it to current/projected base technology program funding. The "Real new & additional" cost is the cost of mock up facilities, plus the cost of the "test articles" themselves. Spending on these does not start until a few years from now.

22 Some General Remarks The US ITER-TBM team has consistently made the point that the ITER-TBM activities are a joint effort among the Plasma Chamber, Materials, PFC, Safety, and Tritium Programs. We have always operated this way and this has tremendously benefited the US effort. This joint partnership needs to continue and to be strengthened International collaboration is a necessity and is very consistent with the spirit of the ITER project. The US must continue to lead in the push toward more international collaboration on ITER TBM We should remember that we have evolved a strategy for the US ITER-TBM with considerable "flexibility" in adjusting to different budget scenarios. Examples of variables that help provide such flexibility are: a) phasing / scheduling of the test articles insertions into ITER during its years of operation; b) collaboration with other partners; c) technically effective back-up plan if technical results are negative (e.g., if the insert in the DCLL does not work, we have developed a set of meaningful other tests with the same test articles)