1. Suggested US Plans and Strategy for ITER Test Blanket Mohamed Abdou Presented at APEX/TBM Meeting, UCLA, November 3-5, 2003

2. US Plans and Strategy for ITER TBM Emerging Key Points: 1.The US will have strong participation 2. The US will redirect a large part of its blanket program resources to focus on R&D for ITER TBM 3.The US must rethink its previously preferred two blanket concepts in view of new technical results obtained over the past few years Extensive deliberations have occurred in the US fusion community over the past few months about the US strategy and approach to the ITER TBM (cont’d next page)

3. US Plans and Strategy for ITER TBM (cont’d) 4.There is a need for all ITER Parties to collaborate more, and to possibly consider a more integrated plan among the ITER Parties for carrying out the R&D and construction of the test modules. Among the reasons: a.Spirit of “international collaboration” inherent for the ITER process b.Many new technical issues identified for all blanket concepts c.Failure to resolve key technical issues, such as tritium permeation barriers and MHD insulators. d.The R&D effort and TBM construction and testing will cost much more than previously thought e.Funding for fusion in general, and blankets in particular, remains constrained for ALL the Parties involved

4. What Should the TWO US Blanket Options be for ITER TBM? And How to make the Decision? Emerging View in the US Blanket Community: 1.He-cooled Solid Breeder (pebble bed) Blanket with FS − Selected by all parties (EU, J, RF) and has the largest world R&D − US has highly focused R&D in niche areas and rich expertise in underlying technical disciplines − Suggested US Strategy: − Select He/SB/FS as an option but do not have an independent TBM. Rather, plan on unit cell and submodule test articles that focus on particular technical issues of interest to all parties (Strategy will work if collaboration is agreed to by EU, J) 2.Liquid Breeder Option: ?? − ALL Liquid Breeder Options have serious feasibility, “Go-No-Go” issues. To make a prudent decision, the US needs to initiate a 1 to 2 year study supported by highly focused R&D (time schedule is also a problem)

5. Liquid Breeder Blanket Options of Interest to US and Key Feasibility Issues 1. Self-Cooled Li / V 1.A. Li / V was the US choice for a long time. But negative results and lack of progress on serious feasibility issues are ALARMING 2. Lead-Lithium MHD Effects Corrosion at High Temperature (coupled to coating development) Coating Development, Crack Tolerance Engineering Design Solutions (that may not require coating) Tritium Recovery and Control V Development 2.A. He-Cooled Pb-Li with FS Tritium Permeation (Barrier Development), and Control Corrosion 2.B. Dual Coolant with He-Cooled First Wall and Self-Cooled –Pb-Li breeding zone with SiC INSERT for electrical/thermal insulation (all structure FS) SiC insert compatability with Pb-Li (Corrosion temperature limit) SiC insert performance integrity (cracks in coating of the insert, etc.) Tritium Permeation and Control 1. Self-Cooled Li / V 1.A. Li / V was the US choice for a long time. But negative results and lack of progress on serious feasibility issues are ALARMING 2. Lead-Lithium MHD Effects Corrosion at High Temperature (coupled to coating development) Coating Development, Crack Tolerance Engineering Design Solutions (that may not require coating) Tritium Recovery and Control V Development 2.A. He-Cooled Pb-Li with FS Tritium Permeation (Barrier Development), and Control Corrosion 2.B. Dual Coolant with He-Cooled First Wall and Self-Cooled –Pb-Li breeding zone with SiC INSERT for electrical/thermal insulation (all structure FS) SiC insert compatability with Pb-Li (Corrosion temperature limit) SiC insert performance integrity (cracks in coating of the insert, etc.) Tritium Permeation and Control

6. Liquid Breeder Blanket Options (cont’d) 3. Molten Salt (Flibe/Flinabe) 3.A. Self-Cooled FLiBe with advanced FS structure 3.B. Self-Cooled FLiNaBe with FS structure Enhancing heat transfer and MHD effects on heat transfer Redox, tritium recovery and control

7. Emerging US Plan for ITER TBM Activities (Still in the discussion stage) 1.Join ITER Test Blanket Working Group (TBWG) (Done) 2.Initiate Evaluation Study to select Two Blanket options for US ITER TBM (primarily a selection of which liquid breeder option to choose, since there is an agreement on the specifics of the solid breeder option) − Study is to be led by the Chamber/Blanket Community in partnership with Materials, PFC, Safety, and Advanced Design Communities. Study will involve interactions with EU, Japan, RF, S. Korea, and China. − Study must be based on quantitative modeling and R&D data. Strive to eliminate “historical” bias. − Need to make the selection in 1 to 2 years (to meet ITER schedule) − Participation by other ITER Parties is highly encouraged 3.Initiate R&D and refocus existing activities to address the top-level critical issues that have the highest impact on Selection of Liquid Breeder Option − (e.g., see list given earlier. Examples are MHD insulators, MHD engineering design solutions and experiments, SiC insert corrosion with PbLi, tritium permeation barrier, etc.)

8. Emerging US Plan for ITER TBM Activities (cont’d) 4.Initiate discussions with other ITER Parties about the strategy for ITER TBM, e.g., − Focus on 2 blanket options for the World instead of 2 options per party? − Bi-lateral and multi-lateral collaboration on the R&D (as well as construction of the ITER test articles?) 5.Enhance and focus current international collaborative programs (e.g., JUPITER-II, IEA, etc.) to provide data for ITER Test Module Selection and Development 6.Concurrently develop engineering scaling and engineering design of test articles in the ITER environment for the Blanket concepts selected for testing in ITER

9. What we need to accomplish in this meeting on ITER Test Blanket Module (TBM) Program 1.Plan for a study to select two US favored blanket concepts -Technical issues to be addressed, starting date, organization, etc. 2.Plan for TBM R&D -Summary of current R&D activities relevant to ITER TBM -List and priority of other R&D items that need to be initiated 3.Organization of the US Blanket Community Effort 4.Strengthening interactions with other VLT elements (Materials, Safety and Tritium), PFC, Advanced Design Studies) -A telephone line will be made Wednesday at 1:00 pm for off- site participants 5.Plans for TBWG and international collaboration