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

Slides:



Advertisements
Similar presentations
1 Summary Slides on FNST Top-level Technical Issues and on FNSF objectives, requirements and R&D Presented at FNST Meeting, UCLA August 18-20, 2009 Mohamed.
Advertisements

TITAN/IEA Liquid Breeder collaboration topics and technical issues Dai-Kai Sze, UCSD Presented at the FNS/TBM meeting UCLA, September 19-20, UCLA.
What is Dual Coolant Blanket? Siegfried Malang 2 nd EU-US DCLL Workshop2 nd EU-US DCLL Workshop University of California,University of California, Los.
September 15-16, 2005/ARR 1 Status of ARIES-CS Power Core and Divertor Design and Structural Analysis A. René Raffray University of California, San Diego.
US TBM Activities Update 1- Quick background 2- Recent Activities Mohamed Abdou FNST Meeting held at UCLA, August 2-4,
FNST / PFC / Materials / FNSF Meeting (s) August 2-6, 2010 at UCLA Welcome All Participants to UCLA If there is anything we can do to make the meeting.
US TBM Activities and Collaboration Discussion Mohamed Abdou FNST Meeting held at UCLA, August 18-20, 2009.
FNSF Blanket Testing Mission and Strategy Summary of previous workshops 1 Conclusions Derived Primarily from Previous FNST Workshop, August 12-14, 2008.
Summary and Closing Remarks Farrokh Najmabadi University of California San Diego Presentation to: ARIES Program Peer Review August 18, 2000 UC San Diego.
November 4-5, 2004/ARR 1 ARIES-CS Power Core Options for Phase II and Focus of Engineering Effort A. René Raffray University of California, San Diego ARIES.
November 8-9, Blanket Design for Large Chamber A. René Raffray UCSD With contributions from M. Sawan (UW), I. Sviatoslavsky (UW) and X. Wang (UCSD)
1 Brief Status of ITER TBM A High-Level Ad Hoc Group (AHG) met April 10-11, per request of the ITER Council. In that meeting, Parties intentions were stated,
Thoughts on Fusion Nuclear Technology Development and the Role of ITER TBM Farrokh Najmabadi Prof. of Electrical Engineering Director of Center for Energy.
Thermofluid MHD issues for liquid breeder blankets and first walls Neil B. Morley and Sergey Smolentsev MAE Dept., UCLA APEX/TBM Meeting November 3, 2003.
Material System Design Studies of High Temperature Gas-Cooled Solid Breeder Blanket Module A.Hasegawa (Tohoku Univ.) A.Shimizu, T.Yokomine (Kyushu Univ.)
Power Extraction Research Using a Full Fusion Nuclear Environment G. L. Yoder, Jr. Y. K. M. Peng Oak Ridge National Laboratory Oak Ridge, TN Presentation.
ITER Test Blanket Module and the Need for Coordination Outline What ITER means for the World Technology / Chamber / Blanket Community ITER Plans for TBM.
1 Test Blanket Module (TBM) Briefing to DOE/OFES and US ITER Project Management Mohamed Abdou Video Conference, September 9, 2004 ITER Program.
Briefings to the Materials Community on ITER Test Blanket Module (TBM) Mohamed Abdou August 11, 2003 Outline 1.What is going on with ITER and TBWG 2.Other.
Fusion: Bringing star power to earth Farrokh Najmabadi Prof. of Electrical Engineering Director of Center for Energy Research UC San Diego NES Grand Challenges.
MHD Modeling and Experiments at UCLA for the ITER Test Blanket Program N. Morley, M. Abdou, A. Ying, S. Smolentsev, M-J. Ni, T. Sketchley, J. Burris, M.
Dec 12-14, 2005TBM Planning and Costing Meeting DCLL R&D Evaluations Summary Compiled by Neil Morley for the TBM Planning and Costing Meeting Dec 12-14,
October 27-28, 2004 HAPL meeting, PPPL 1 Thermal-Hydraulic Analysis of Ceramic Breeder Blanket and Plan for Future Effort A. René Raffray UCSD With contributions.
1 Mohamed Abdou With input from M. Sawan (UW), D. Sze (UCSD), N. Morley (UCLA), C. Wong (GA), S. Willms (LANL), A.Ying (UCLA), R. Nygren (SNL), P. Fogarty.
CESTAR Briefing Mohamed Abdou CESTAR Meeting, Rice Room, Boelter Hall April 28, 2006.
1 VLT Research Highlights ITER Test Blanket Module (TBM) M. Abdou and the ITER-TBM Team Outline 1.Introduction and TBWG activities 2.Technical planning.
February 5-6, 2004 HAPL meeting, G.Tech. 1 HAPL Blanket Strategy A. René Raffray UCSD With contributions from M. Sawan and I. Sviatoslavsky UW HAPL Meeting.
ITER test plan for the solid breeder TBM Presented by P. Calderoni March 3, 2004 UCLA.
Overview of UCLA Research Activities on Fusion Nuclear Science and Technology Briefing to Professor Osamu Motojima and Japanese delegation from NIFS and.
Conference Call, June 23, 2005 Remarks on US Costing Activities for the US ITER-TBM Mohamed Abdou.
1 ITER Test Blanket Module (TBM) and ITER Nuclear Science and Engineering Mohamed Abdou VLT/USIPO Meeting, October 20-21, 2004.
Pacific Northwest National Laboratory U.S. Department of Energy TBM Structure, Materials and Fabrication Collaboration Issues R.J. Kurtz 1, and A.F. Rowcliffe.
Fusion Energy Sciences Program Department of Energy Perspective February 23, E xcellent S cience in S upport of A ttractive.
1 -TBWG next meeting 8 - Presentation of Parties, in particular on action 17 and action 19 (TBWG-15), including: Progress of work Impact on TBMs of frame.
US Test Blanket Module Partially Integrated Testing Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for.
Introductory Remarks and Highlights of FY02 Plan Mohamed Abdou APEX Meeting, Scottsdale, AZ November 7-9, 2001 APEX Outline Key Points from FY01 FY02 PLAN.
Introductory Remarks to APEX/TBM* Meeting November 3-5, 2003 Mohamed Abdou *ITER Test Blanket Module.
Materials Integration by Fission Reactor Irradiation and Essential Basic Studies for Overall Evaluation Presented by N.Yoshida and K.Abe At the J-US Meeting,
Various Strategies for DCLL in the US Technology Program Poor ITER utilization (Lowest Cost Scenario) - Support EU HCLL effort, no independent DCLL TBM.
Advanced Design Activities in US Farrokh Najmabadi University of California, San Diego Japan/US Workshop on Fusion Power Plants & Related Technologies.
UCLA - March 8, 2006 US TBM Cost Estimate Status March 8, 2006 Tom Mann.
Plan for IEA LB Workshop Dai-Kai Sze, UCSD PattrickCalderoni, INL Fusion Nuclear Science and Technology Meeting UCLA, August 2-4, 2010.
Tritium Permeation Issue, Plan and Progress Dai-Kai Sze University of California, San Diego Presented at the ITER TBM Project Meeting UCLA, Feb ,
March 3-4, 2005 HAPL meeting, NRL 1 Assessment of Blanket Options for Magnetic Diversion Concept A. René Raffray UCSD With contributions from M. Sawan.
1 Discussion with Drs. Kwon and Cho UCLA-NFRC Collaboration Mohamed Abdou March 27, 2006.
Overview of the US ITER Test Blanket Module (TBM) Technical Plan
Material System Thermomechanics Interactions (cont’d) International Collaboration: Role / Impact / Recognition - Serves a unique role in IEA program on.
HAPL June 20-21, Overview of Chamber/Blanket Work Presented by A.R. Raffray UCSD With contributions from CTC Group and MWG Blanket contributions:
Highlights of US ITER TBM Technical Plan and Cost Estimates (and Impact of International Collaboration) Mohamed Abdou and the U.S. Team TBWG-17 Presented.
“Report on TBWG Meeting” Mohamed Abdou Presented at APEX / ITER-TBM Meeting November 3 – 5, 2003 UCLA, Los Angeles, CA TBWG-11 Meeting at Garching, Germany,
Fusion: The Energy Source for the XXI Century Mohamed Abdou Distinguished Professor, Mechanical and Aerospace Engineering Department Director, Center for.
US Participation in the
Overview of Fusion Blanket R&D In Japan
Some General Guidelines for the US TBM Costing
Introductory Remarks and Meeting Goals
Material Issues for the US ITER-TBM Program
Can We achieve the TBR Needed in FNF?
Thermo-mechanical Analysis
Tritium Research in TITA Information Required
Advanced Design Activities in US
“Report on TBWG Meeting”
VLT Meeting, Washington DC, August 25, 2005
Remarks on US Costing Activities for the US ITER-TBM
Introductory Remarks to APEX/TBM* Meeting November 3-5, 2003
Mohamed A. Abdou Summary, Approach and Strategy (M. Abdou)
US TBM Cost Activity Tom Mann December 12 – 14, 2005.
Presented at the ITER TBM Meeting, February 23-25, 2004, at UCLA
Compiled by Neil Morley for the TBM Conference Call Nov. 17, 2005
University of California, San Diego
Presentation transcript:

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

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)

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

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)

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

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

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.)

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

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