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General Comments on the Development of Future Fusion PFCs presented by Richard E. Nygren

General Comments on the Development of Future Fusion PFCs presented by Richard E. Nygren Sandia National Laboratories ARIES High Heat Flux Components Workshop UCSD 10-12 December 2008.

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General Comments on the Development of Future Fusion PFCs presented by Richard E. Nygren

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  1. General Comments on the Development of Future Fusion PFCs presented by Richard E. Nygren Sandia National Laboratories ARIES High Heat Flux Components Workshop UCSD 10-12 December 2008 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. RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  2. BROAD SCOPE Tokamak/AT Focus: 1. tokamak divertors 2. solid surface PFCs 3. present/ITER-DEMO gap Other: 4. alternates 5. liquid surface 6. other fusion pathways Alternates RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  3. BROADSCOPE Tokamak/AT ITER divertor JET DIII-D JT-60U C-MOD ASDEX-U TEXTOR Tore Supra TFTR Alternates MAST NSTX LHD W7X Wendelstein Non-electric or hybrid applications RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  4. BROADSCOPE Tokamak/AT DEMO-A divertor ITER divertor DEMO-B divertor JET DIII-D JT-60U ??? ??? C-MOD ASDEX-U TEXTOR Tore Supra TFTR ???/CTF Alternates MAST ?? primary alternate NSTX ??? LHD ??? W7X Wendelstein Non-electric of hybrid applications RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  5. D/T plasma • solid surface • long pulse • good efficiency • high availability • damage resistance BROADSCOPE Tokamak/AT DEMO-A divertor ITER divertor DEMO-B divertor JET DIII-D JT-60U ??? ??? C-MOD ASDEX-U TEXTOR Tore Supra TFTR ???/CTF Alternates MAST ?? primary alternate NSTX ??? LHD ??? W7X Wendelstein • ?liquid surface Non-electric of hybrid applications RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  6. D/T plasma • solid surface • long pulse • good efficiency • high availability • damage resistance • tritium retention • active cooling • high temperature • high reliability • neutron damage WORKSHOP SCOPE Tokamak/AT DEMO-A divertor ITER divertor DEMO-B divertor JET DIII-D JT-60U ??? ??? C-MOD ASDEX-U TEXTOR Tore Supra TFTR ???/CTF GAP 1 GAP 2 RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  7. active cooling • tritium retention • high temperature • high reliability • neutron damage GAP 1 GAP 2 WORKSHOP SCOPE RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  8. Tech. Alt’s. physics tokamak • active cooling • tritium retention • high temperature • high reliability • neutron damage GAP 1 GAP 2 OTHER SCOPE GAP X GAP Y RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  9. SOURCES Tokamak/AT ITER divertor DEMO-A divertor JET DEMO-B divertor DIII-D JT-60U ??? ??? C-MOD ASDEX-U TEXTOR Tore Supra TFTR D Maisonnier et al., DEMO and Fusion Power Plant Conceptual Studies in Europe Nucl. Fusion 47 (2007) ISFNT7 K. Lackner SOFT2006 G Federici et al., Key ITER plasma edge and plasma–material interaction issues, JNM 313–316 (2003) PSI J Linke et al., High heat flux testing of plasma facing materials …, JNM 367–370 (2007) V Philipps Plasma–wall interaction, a key issue on the way to a steady state burning fusion device, Phys. Scr. T123 (2006) RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  10. Sources Tokamak/AT ITER divertor DEMO-A divertor JET DEMO-B divertor DIII-D JT-60U ??? ??? C-MOD ASDEX-U TEXTOR Tore Supra “Greenwald” Panel Report Priorities, Gaps and Opportunities: Towards A Long-Range Strategic Plan For Magnetic Fusion Energy, FESAC Oct 2007 TFTR D Whyte The Challenges of Plasma-Surface Interactions for ITER & Beyond, to FESAC Nov 2008 D Maisonnier et al., DEMO and Fusion Power Plant Conceptual Studies in Europe Nucl. Fusion 47 (2007) ISFNT7 K Lackner SOFT2006 US ReNew Activity G Federici et al., Key ITER plasma edge and plasma–material interaction issues, JNM 313–316 (2003) PSI J Linke et al., High heat flux testing of plasma facing materials …, JNM 367–370 (2007) V Philipps Plasma–wall interaction, a key issue on the way to a steady state burning fusion device, Phys. Scr. T123 (2006) RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  11. “Greenwald” Panel Report “The themes were defined in terms of knowledge required prior to Demo. ... based on sound scientific principles and rigorously tested in the laboratory so that the step to a [DEMO] .. taken with high confidence of success. RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  12. “Greenwald” Panel Report “The themes were defined in terms of knowledge required prior to Demo. ... based on sound scientific principles and rigorously tested in the laboratory so that the step to a [DEMO] .. taken with high confidence of success. Theme B. Taming the Plasma Material Interface: .. knowledge sufficient to design and build, with high confidence, 8. PWI: Understand and control of all processes that couple the plasma and nearby materials. 9. PFCs: Understand .. materials and processes that can be used to design replaceable components that can survive .. 10. .. Other .. : .. necessary understanding of plasma interactions, neutron loading and materials to allow design of .. any other diagnostic equipment that can survive ... RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  13. “Greenwald” Panel Report Theme C. Harnessing fusion power: knowledge .. sufficient to design and build, with high confidence, 11. Fuel Cycle: .. manage the flow of tritium ... 12. Power: .. temperatures sufficiently high for efficient production of electricity or hydrogen. 13. Materials ..: Understand the basic materials science for fusion breeding blankets, structural components, plasma diagnostics and heating components .. high neutron fluence .. 14. Safety: Demonstrate .. safety …. minimize environmental burdens .. 15. RAMI [Reliability, Availability, Maintainability & Inspectability]: Demonstrate .. productive capacity …. validate economic assumptions …. RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  14. “Greenwald” Panel Report Finding 6. Evaluation of current and planned programs and summary of gaps ….. The most significant gaps were:G1. …. G2. … G-5. Ability to predict and avoid, or detect and mitigate, off-normal plasma events … G-9. Sufficient understanding of all plasma-wall interactions …. The science underlying the interaction of plasma and material needs to be significantly strengthened to .. G-10. Understanding of the use of low activation solid and liquid materials, joining technologies and cooling strategies ... G-11. Understanding .. the complete fuel cycle, particularly .. G-12. An engineering science base .. effective removal of heat ... G-13. Understanding .. low activation materials .. G-14. .. guarantee safety over the plant life cycle - including .. G-15. .. efficient maintainability of in-vessel components .. RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  15. “Greenwald” Panel Report Recommendation 4. .... nine major initiatives. I-1. .. predictive plasma modeling and validation .., I-2. Extensions to ITER AT capabilities .. burning AT regimes I-3. Integrated advanced burning physics …facility .. dedicated I-4. Integrated experiment for PWI/PFCs .. steady-state .. non-DT I-5. .. disruption-free concepts .. performance extension device .. I-6. .. advanced computer modeling and laboratory testing .. single-effects science for major fusion technology issues, I-7. Materials qualification facility … (IFMIF). I-8. Component development/testing program … multi-effect issues in critical technology .. breeding/blanket .. first wall I-9. Component qualification facility.. high availability.. heat flux .. neutron fluence .. DT device .... (CTF). RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  16. D Whyte FESAC Presentation “The Challenges of PSI for ITER & Beyond” Nov 2008 Issue/Gap tokamaks ITER CTF DEMO now • Quiescent energy exhaust • Transient energy exhaust from plasma instabilities • Yearly neutron damage in plasma-facing materials • Max. gross material removal rate with 1% erosion yield • Tritium consumption greatly increasing parameters RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  17. D Whyte FESAC Presentation “The Challenges of PSI for ITER & Beyond” Nov 2008 • Lack basic understanding and diagnosis of PSI processes in fusion devices → Uncertain extrapolation • Heat exhaust is primary design point for edge materials, since this Is directly related to fusion power density • Thermal efficiency .. high ambient T → Fundamentally different Physical Chemistry .. completely unexplored in fusion devices • Energy sustainment chasm to CTF & DEMO • Rapid dissipation of plasma thermal energy poses major challenges in any Demo • consequences of large particulate removal on .. plasma .. & safety • Tokamak edge plasmas feature extreme spatial gradients and fluctuations levels, .. erosion prediction & control very difficult • It is hard to overstate the importance of ambient temperature for fuel control & T retention • 30+ years of experience .. we should be worried/excited .. in particular the effects of having “hot walls” RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  18. Power plant conceptual studies in Europe D. Maisonnier, D. Campbell, I. Cook, Nucl. Fusion 47 (2007) 1524–1532 [ISFNT7] RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  19. Power plant conceptual studies in Europe D. Maisonnier, D. Campbell, I. Cook, Nucl. Fusion 47 (2007) 1524–1532 [ISFNT7] RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  20. Power plant conceptual studies in Europe D. Maisonnier, D. Campbell, I. Cook, Nucl. Fusion 47 (2007) 1524–1532 [ISFNT7] RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  21. Power plant conceptual studies in Europe D. Maisonnier, D. Campbell, I. Cook, Nucl. Fusion 47 (2007) 1524–1532 [ISFNT7] RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  22. High temperature He-cooled divertor Need for work on divertor systems RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  23. Whose DEMO? In contrast to the rest of the world, a typical preference of US technology people has been • one step to high tech DEMO (reactor prototype) • parallel R&D for materials and blankets (CTF) RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  24. Whose DEMO? In contrast to the rest of the world, a typical preference of US technology people has been • one step to high tech DEMO (reactor prototype) • parallel R&D for materials and blankets (CTF) We have a great challenge to develop the needed technology! ITER activity is a revealing as we observe the need for definition and integration in the design along with the need to move forward in building the machine! RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  25. We develop PFCs using single effects tests J. Linke et al., JNM 367–370 (2007) 1422–1431 RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  26. We love issues We are good at developing issues • We tend to • be optimistic (we are in fusion after all) • enjoy identifying issues and pondering problems • look toward R&D programs Congratulations on your new issue. Hey – nice issue You rAPER Raised some important issues I RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  27. M a t ’l s d e v el o p m e n t PWI & PFC tests component dev./qual GAP 3: Technology Culture We develop one-of-a kind units with anecdotal mockup tests. PWI tests tokamak coupons test PFC Material A lab tests lab tests rad effects testing properties properties 2 PFC tests Material A mockups prototypes prototypes joining tests tests tests Material B scale up manufacturing manufacturing development components Vendor qual. acceptance design validation QA development RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  28. M a t ’l s d e v e l o p m e n t PWI & PFC tests component dev./qual GAP 3: Technology Culture Configuration d e v e l o p m e n t STs, others Ergodic div. Super-X div. Liquid PFCs A realistic “fully funded”technology program, will involve a strong winnowing of choices for PFC materials and divertor technology simply because of the time to develop and prove specific robust components for a DEMO. RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  29. PROGRAM & DESIGN INTEGRATION knowledge .. sufficient to design and build, with high confidence, Recall some excerpts from the “Greenwald” panel report: 9. PFCs: Understand .. materials and processes … design replaceable components that can survive .. I-3. Integrated advanced burning physics …facility .. dedicated I-4. Integrated experiment for PWI/PFCs .. steady-state .. non-DT I-8. Component development/testing program … multi-effect issues in critical technology .. breeding/blanket .. first wall RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

  30. E N D RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD

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