Requirements for FNSF and DEMO

Transcription

1 FNST Meeting 2-4 August 2010, UCLA A Historical Perspective on Test Stands for R&D in PFC/PMI and their role in addressing Requirements for FNSF and DEMO Richard Nygren and Matthew Baldwin 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 FNST/PFC/MASCO under Meeting contract - UCLA DE-AC04-94AL August 2-6,

2 PFC/Matls PSI Plasma/edge PFCS/HHF - PSI Physics in all metal devices ASDEX-U (divertor) Alcator C-MOD (divertor) Others: TRIAM-U (limiter) JET with ITER-like divertor R&D on W PFCs JET ITER-like divertor (W monoblocks & coatings) Coatings in ASDEX-Upgrade W limiters in TEXTOR, HT-7 Fabrication development High heat flux testing Probe/tiles measurements - W erosion in DIII-D and C-MOD - D or He damage in TRIAM, LHD Lab measurements (PISCES,..) Nature of inquiry ADEX-Upgrade Can we run with W walls? How do we form and sustain a plasma? How is power distributed? Where does eroded W go? C-Mod Mo tiles Will it perform well? What are likely failures? How can we improve? DiMES DIII-D ARIES surface probes

3 1. What do we know? Some useful questions: 2. What recent changes affect past conclusions? (reevaluation) For PFC/PMI area: ITER shaped wall Li pumping (NSTX, LTX) & LMMHD for liquid PFCs Surface effects and damage in tungsten New opportunities, e.g. new devices (EAST) Divertor options (super-x) 3. What do we want to build? DEMO via FNSF, supporting R&D 4. What can we build? Roll forward viewpoint 5. What should we build? FNS Pathways Assessment, follow-on

4 FNST - Fusion Nuclear Science & Technology FNST PFC/PMI Focus FNST R&D investment Planning R&D Capability FNST studies: Blanket/PFC: PFC/HHF PSI DTMPG* Li, LLD *DT Mat l Physics Group FELIX (EM) Blanket tritium in TFTR ALEX (MHD) MTOR (MHD) corrosion loops SNL LANL INL TPX TPE Tritium & Safety TSTA STAR Materials EBR-II, FFTF HFIR, ATR damage FMIT IFMIF RTNS-II ETR/FED FINESSE... ANL DEMO BCSS VENUS.. IEA EU APEX BCSS ALPS PPS (EU) [4 cases] TITAN & TBM --- ESURF PMTF DiMES PISCES lab PSI probes Chambers STOX, LAMPE DPE ANL Purdue, DIONYSIS (MIT)

5 FNST - Fusion Nuclear Science & Technology FNST PFC/PMI Focus Overlay relation to progress in confinement PISCES (Conn/Goebel, UCLA) PISCES (Doerner, UCSD) Be upgrade TPX (Causey)--- TPE STAR Codep (Hsu) SNL (tritium INL Conditioning (Wilson) [LAMPE/Penning, STOX] DiMES (DIII-D) SSS (C-MOD) lab PSI probes SNL, ANL ANL Purdue, UofI, DIONYSIS (MIT) ESURF PMTF FELIX (EM)

6 limiters isolated core radiation loss sputtering FNST - Fusion Nuclear Science & Technology FNST PFC/PMI Focus more power in plasma conditioned/coated wall erosion-consequence [CX neutrals, Maxwellian tail] *DT Mat l Physics Group tritium in TFTR limiters divertors power impurities PISCES (Conn/Goebel, UCLA) PISCES (Doerner, UCSD) Be upgrade TPX (Causey)--- TPE STAR Codep (Hsu) SNL (tritium INL Conditioning (Wilson) [LAMPE/Penning, STOX] DiMES (DIII-D) SSS (C-MOD) lab PSI probes SNL, ANL ANL Purdue, UofI, DIONYSIS (MIT) ESURF PMTF FELIX (EM)

7 limiters isolated core radiation loss sputtering FNST - Fusion Nuclear Science & Technology FNST PFC/PMI Focus more power in plasma conditioned/coated wall erosion-consequence [CX neutrals, Maxwellian tail] *DT Mat l Physics Group tritium in TFTR diverted plasmas [more core isolation] [radiative, detached div.] importance of plasma edge limiters divertors active cooling some issues, C power impurities JET uses Be PFC options for ITER PISCES (Conn/Goebel, UCLA) PISCES (Doerner, UCSD) Be upgrade TPX (Causey)--- TPE STAR Codep (Hsu) SNL (tritium INL Conditioning (Wilson) [LAMPE/Penning, STOX] DiMES (DIII-D) SSS (C-MOD) lab PSI probes SNL, ANL prominence of ITER tritium retention ANL Purdue, UofI, DIONYSIS (MIT) ESURF PMTF FELIX (EM)

8 limiters isolated core radiation loss sputtering FNST - Fusion Nuclear Science & Technology FNST PFC/PMI Focus more power in plasma conditioned/coated wall erosion-consequence [CX neutrals, Maxwellian tail] *DT Mat l Physics Group tritium in TFTR limiters divertors active cooling power impurities diverted plasmas [more core isolation] [radiative, detached div.] importance of plasma edge prominence of ITER tritium retention some issues, C JET uses Be PFC options for ITER PISCES (Conn/Goebel, UCLA) large D/T devices exhausted power stored energy?fnsf/demo div. PISCES (Doerner, UCSD) Be upgrade TPX (Causey)--- TPE STAR Codep (Hsu) SNL (tritium INL Conditioning (Wilson) [LAMPE/Penning, STOX] DiMES (DIII-D) SSS (C-MOD) lab PSI probes SNL, ANL ANL Purdue, UofI, DIONYSIS (MIT) Hot walls Shaped FW?super-X ESURF PMTF FELIX (EM)

9 limiters isolated core radiation loss sputtering FNST - Fusion Nuclear Science & Technology FNST PFC/PMI Focus more power in plasma conditioned/coated wall erosion-consequence [CX neutrals, Maxwellian tail] *DT Mat l Physics Group tritium in TFTR PISCES (Conn/Goebel, UCLA) diverted plasmas [more core isolation] [radiative, detached div.] importance of plasma edge large D/T devices exhausted power stored energy?fnsf/demo div. Hot walls limiters divertors active cooling some issues, C Shaped FW power impurities JET uses Be?super-X PFC options for ITER PISCES (Doerner, UCSD) Be upgrade TPX (Causey)--- TPE STAR Codep (Hsu) SNL (tritium INL Conditioning (Wilson) [LAMPE/Penning, STOX] DiMES (DIII-D) SSS (C-MOD) lab PSI probes SNL, ANL prominence of ITER tritium retention ANL Purdue, UofI, DIONYSIS (MIT) ESURF PMTF FELIX (EM) Upgraded & new capabilities Heat+Ions Super PISCES?

10 1. What do we know? Some useful questions: 2. What recent changes affect past conclusions? (reevaluation) For PFC/PMI area: ITER shaped wall Li pumping (NSTX, LTX) & LMMHD for liquid PFCs Surface effects and damage in tungsten New opportunities, e.g. new devices (EAST) Divertor options (super-x) 3. What do we want to build? DEMO via FNSF, supporting R&D 4. What can we build? Roll forward viewpoint 5. What should we build? FNS Pathways Assessment, follow-on

11 from 35 year plan FESAC Fusion Dev. Path Panel Tech. & Comp. Testing Mat ls Testing

12 PFC Acceptance/Deployment Lab Tests Device Test (?EAST) FNSF The acceptance/use of materials is a cycle of materials development and experience in application. This is challenging, time-consuming and needs strong coordination with plasma devices on interfaces and with industrial suppliers on fabrication development, QA and acceptance. e.g., Tore Supra and ITER. robust actively-cooled PFCs materials development component development - design confirmation [modeling, testing] - fabrication dev. - QA & acceptance Tore Supra water cooled PFCs modular limiters in 1990s failed very good history working closely with Plansee on fabrication yet still had quality problems rebuilt PFCs - CIEL done 2002

13 PFC Acceptance/Deployment Lab Tests Device Test (?EAST) FNSF The acceptance/use of materials is a cycle of materials development and experience in application. Heat+Ions Super PISCES? ITER FW Activity FW Quality Mockup Tests Series 1: US & EU Mockups Series 2: JA, RF, PRC, KO 10,000 cycles + MARFE test robust actively-cooled PFCs materials development component development - design confirmation [modeling, testing] - fabrication dev. - QA & acceptance ~25y - fusion-specific water-cooled PFCs ~15y - ITER PFC R&D ~10y detailed R&D ITER design changing ~ 4y FWQ mockups vendors engaged 3-5y final design to fab

14 E N D

15 W-related PSI research: processes D X He T Y Z reflect, sputter X D Y erode redeposit implant, displace (dpa) D He T Y Z deposited layer X T He T adsorb* recombine* trap* bond* evolve voids* alter properties* T diffuse/permeate* T T T T T displace (dpa), transmute dpa n n He X rad. creep, hardening resistivity, µ(permeability) n M transmute evolve voids* alter properties* n melt, vaporize q vapor shield* recrystallize* crack/craze* *temperature dependent behavior

16 ITER GAP Tokamak/AT DEMO-A divertor DEMO-B JET ITER divertor JT-60U C-MOD DIII-D??? TEXTOR ASDEX-U D/T plasma solid??? surface Tore Supra long pulse divertor TFTR Alternates MAST?liquid surface NSTX????? primary tritium retention LHD alternate active??? cooling W7X Wendelstein DEMO GAP good efficiency high availability damage resistance high temperature high reliability neutron damage Non-electric of hybrid applications

17 Make two modifications: DEMO GAP ITER GAP Tokamak/AT ITER DEMO-A JET divertor divertor DEMO-B JT-60U *Fusion DIII-D Nuclear Science Facility divertor C-MOD??? TEXTOR ASDEX-U D/T plasma solid??? surface good efficiency Tore Supra robust actively-cooled long pulse TFTR PFCs high availability - design confirmation [modeling, damage testing] resistance Alternates materials - fabrication dev. MAST?liquid development surface - QA & acceptance NSTX??? component?? primary tritium development retention LHD alternate active??? cooling high temperature W7X Wendelstein high reliability neutron damage #1 Add FNSF* with hot walls. #2 Prepare Non-electric of hybrid applications

18 Schedule for actively-cooled PFCs Tokamak/AT Satellite/FNSF GAP DEMO GAP ITER DEMO-A JET divertor divertor DEMO-B JT-60U DIII-D??? or divertor C-MODactively cooled upgrade TEXTOR launchers, ASDEX-U D/T plasma probes (IVCs) satellites solid??? surface good efficiency Tore Supra long pulse high availability engineering TFTR H/D gap hot walls??? damage resistance instrumentation Alternates D/T CTF MAST?liquid surface NSTX tritium retention????? primary LHD active cooling high alternate temperature??? high reliability W7X Wendelstein neutron damage Non-electric of hybrid applications