JT-60SA (super advanced) project

Transcription

1 H27 (25min.) 3JUL215 JT-6SA T. Nakano (Japan Atomic Energy Agency) M. Sakamoto (University of Tsukuba) M. Wischmeier (IPP, Germany) Acknowledgements: N. Asakura, C. Gleason-González, K. Hoshino, H. Kawashima, Y. Miyo, S. Sakurai, K. Shimizu, H. Utoh, S. Varoutis C. Day, P. Lang, R. Neu ant JA TROs JT-6SA (super advanced) project The mission of the JT-6SA project is to contribute to the early realization of fusion energy by addressing key physics and engineering issues for ITER and DEMO.! Supportive Researches for ITER ITER operation scenarios is optimized by using break-even-equivalent class hightemperature deuterium plasmas lasting for a duration (~1 s).! Complementary Researches to ITER DEMO operation scenarios is established by long sustainment (~1 s) of high pressure plasmas necessary in DEMO. ITER (France)! Training of Domestic Scientists and Technicians especially those in younger generation who will play leading roles in R&D of ITER and DEMO DT burning JT-6SA HP: JT-6SA Research Plan: References: S. Ishida, P. Barabaschi, Y. Kamada, et al., Nucl. Fusion 51 (211) 9418 Y. Kamada, P. Barabaschi, S. Ishida, et al., Nucl. Fusion 53 (213) 141 P. Barabaschi and the JT-6SA Team, OV/3-2 in Proc. 25th IAEA-FEC (214) Support ITER Foster next generation demonstration of power generation DEMO JT-6SA (superconducting tokamak)

2 Highly Shaped Large Superconducting Tokamak 3 JT-6SA: " Large superconducting tokamak " High plasma current (max. I P =5.5 MA) " Long pulse (typically 1 s) " High heating power (41 MW 1 s) " Highly shaped (S=q 95 I p /(ab T ) ~7, A~2.5) " Full-monoblock carbon DIV, first wall (Option: Metallic wall in later phase) Full I P, 41 MW operation Plasma current, I P (MA) Toroidal magnetic field, B T (T) Major radius, R p (m) Aspect ratio, A Elongation, κ x Triangularity, δ x Safety factor, q 95 Injection power, P in (MW) Normalized beta, β N Bootstrap current ftacution, f BS Non-circular superconducting tokamaks We are here Year Construction Operation Preparation Disassembly Assembly Commissioning Experiment Integrated Commissioning Manufacture of the main components has been going well on schedule in both EU and JA towards the first plasma in 219.

3 Manufacture of the main components going well on schedule in both EU and JA 5 By Oct. 214, 25 Procurement Arrangements (PAs) have been concluded: (JA: 14PAs, EU: 11PAs) = 88% of the total cost of BA Satellite Tokamak Program. JT-6U Disassembly Completed in Oct. 212 Toroidal Field Coils Winding started. Lower 3 EF Coils were placed on the cryostat base. Mar., 213 From Dec, 215 TF coil test facility has been almost completed. First Plasma 219 March Jan. 214 Cryostat Base (26 tons) Tokamak Assembly started in Jan. 213 by installing the cryostat base. Vacuum Vessel Sectors were completed, and VV assembly started in May 214. Upper 3 EF Coils & CS: Manufacture on going. Cryostat: Manufacture started. HTS Current Lead: mass production started. 6 # (14 ) 5 F4E JAEA SOL MHD JT6SA JT-6SA JT-6SA ITER # 182 (1 /, 23 EuroFusion )

4 JT-6SA Research Plan 7 # JT-6SA Research Plan (SARP) summarizes Research items and Strategy for JT-6SA to solve critical issues in ITER and DEMO. # Points of the JT-6SARP " Make a plan " Encourage collaborative studies on JT-6SA " Optimize hard wares: heatings, fueling, pumping, diagnostics, etc. " Growing year by year toward fruitful experiments. v.3.1 (Dec. 213) Chapter 2: Research Strategy Chapter 3: Operation Regime Development Chapter 4: MHD Stability and Control Chapter 5: Transport and Confinement Chapter 6: High Energy Particle Behavior Chapter 7: Pedestal and Edge Physics Chapter 8: Divertor, SOL and PWI Chapter 9: Fusion Engineering Chapter 1: Theoretical models and simulation codes Over 33 colleagues (11 countries, 38 inst.) join activities led by Technical Responsible Officers (TROs) in the research fields. Structure of Research Plan (DSOL/PWI) Peak Heat flux / PCF Mission: Elements: 8-1.Long-pulse high-β, high-density and high-radiative plasma High β Integrate 15 MW/m 2 / C x1s 5 MW/m 2 / W x 1yr 1 MW/m 2 / W x 4s JT-6SA DEMO ITER 8-2 Divertor detachment V-shaped corner High density 8-3 Radiative divertor Ar/Ne seed 8-4.Fueling / exhaust Pellet Gas Pumping 8-5. Impurity C/W transport Wall conditioning Inter-shot cleaning 8-7~9. PWI Retention Erosion W scenario...

5 Scenarios in JT-6SA #1 #2 #3 #4-1 #4-2 #5-1 #5-2 #6 (1) Full Full Full Current Current Current Inductive ITER- Advanced High β High β N Inductive Inductive SN, like Inductive N High β High f N Full-CD GW 3s DN, SN, 3MW Inductive (hybrid) Full-CD 41MW 41MW High density Plasma Current (MA) Toroidal field BT (T) q 95 ~3 ~3 ~3 ~3 ~4.4 ~ ~4 R/a (m/m) 2.96/ / / / / / / /1.11 Aspect ratio A Elongation κ x Triangularity δ x Shape factor S Volume (m 3 ) Cross-section (m 2 ) Normalised beta β N Electron density (1 19 m -3 ) Line-average/volume 6.3/ /5.6 1./9 9.1/ /6.2 / /4.3 / -average Greenwald density, n GW (1 19 m -3 ) / f GW 13/.5 13/.5 13/.8 11/.8 8.6/.8 5.9/ / 5.2/.39 Plasma thermal energy, W TH (MJ) P add (MW) P NNB /P PNB /P EC (MW) 41 1/24/7 41 1/24/7 3 1/2/- 34 1/24/- 37 1/2/7 37 1/2/7 3 6/17/ /6/4 Thermal confinement time, τ Eth (s) H 98(y,2) JT-6SA Research Plan v3.2 Table 3-1, Scenario I p (MA) Scenario 5-1 SONIC simulation for Full-CD, High β plasma B T (T) R p m a p (m) A κ x δ x.5.47 S q V p (m 3 ) P in (MW) H H β N τ E (s) T i () (kev) T e () (kev) n e () (1 19 /m 3 ) n bar e (1 19 / m 3 ) 6.3 n e / n Greenwald.5.85 f BS τ plasma (s) Z (m) χ e = m 2 /s χ i = m 2 /s D =.3 m 2 /s inner targets S pump : 5 m 3 /s P SOL = 37 MW Γ ion SOL = 2.8 x1 21 s -1 Coronal C + MC Ar (n e τ = 1x1 16 s/m 3 ) R (m) outer targets PFC: C Γ D2 Puff = - x1 22 s MW/m 2 x1 s for 3 cycles 1 MW/m 2 x1 s for 1 cycles

6 Only C (Monte-Carlo, Phys+Chem sputtering) Radiative divertor compatible with core plasma for Scenario 5 $Heat load: OK %n e sep (3.4 x1 19 m -3 ): Incompatible with core n e profile (~1.7 x1 19 m -3 ) C (coronal model, nc/ni=5% (div), 1%(others))+ Ar (Monte-Carlo,.86 Pam 3 /s) $Heat load: good $n e sep (1.5 x1 19 m -3 ): Compatible with core n e profile (~1.7 x1 19 m -3 ) %Z eff =2.1-> 2.4, P rad =2.8-> 4.3 MW (N. Hayashi APS214) K. Hoshino, etal, Contrib. Plasma Phys. 54 (214) 44. For further radiation increase, mixture of seeding impurities play roles Ar(main) Ne(div) JT-6U For ITER and DEMO ( 1 and 5 MW/m2 ), systematic studies on the effects of mixed impurities are needed. Ne(div) Ar(main) N. Asakura, T. Nakano, etal, Nucl. Fusion 49 (29) 1151.

7 Scenarios in JT-6SA #1 #2 #3 #4-1 #4-2 #5-1 #5-2 #6 (1) Full Full Full Current Current Current Inductive ITER- Advanced High β High β N Inductive Inductive SN, like Inductive N High β High f N Full-CD GW 3s DN, SN, 3MW Inductive (hybrid) Full-CD 41MW 41MW High density Plasma Current (MA) Toroidal field BT (T) q 95 ~3 ~3 ~3 ~3 ~4.4 ~ ~4 R/a (m/m) 2.96/ / / / / / / /1.11 Aspect ratio A Elongation κ x Triangularity δ x Shape factor S Volume (m 3 ) Cross-section (m 2 ) Normalised beta β N Electron density (1 19 m -3 ) Line-average/volume 6.3/ /5.6 1./9 9.1/ /6.2 / /4.3 / -average Greenwald density, n GW (1 19 m -3 ) / f GW 13/.5 13/.5 13/.8 11/.8 8.6/.8 5.9/ / 5.2/.39 Plasma thermal energy, W TH (MJ) P add (MW) P NNB /P PNB /P EC (MW) 41 1/24/7 41 1/24/7 3 1/2/- 34 1/24/- 37 1/2/7 37 1/2/7 3 6/17/ /6/4 Thermal confinement time, τ Eth (s) H 98(y,2) JT-6SA Research Plan v3.2 Table 3-1, Scenario I p (MA) Scenario 2 SONIC simulation for Full-Ip & heating plasma B T (T) R p m a p (m) A κ x δ x.5.47 S q V p (m 3 ) P in (MW) H H β N τ E (s) T i () (kev) T e () (kev) n e () (1 19 /m 3 ) n bar e (1 19 / m 3 ) 6.3 n e / n Greenwald.5.85 f BS τ plasma (s) Z (m) χ e = m 2 /s χ i = m 2 /s D =.3 m 2 /s inner targets S pump : 5 m 3 /s P SOL = 37 MW Γ ion SOL = 2.8 x1 21 s -1 Coronal C (n e τ = 1x1 16 s/m 3 ) R (m) outer targets PFC: C Γ D2 Puff = - x1 22 s MW/m 2 x1 s for 3 cycles 1 MW/m 2 x1 s for 1 cycles

8 High neutral compression predicted in the V-shaped corners 3x1 2 m -3 3x1 2 m -3 High neutral density in the V-shaped corner is predicted by SOLDOR simulation for the case with I p of 5.5 MA, P heat of 41 MW, Γ gas of 1.5x1 22 /s and S pump of 5 m 3 /s. H. Kawashima, et al, J Nuc Mater 415 (211) S948. 6% radiation in the divertor predicted P rad In =6.2 MW 7 MWm -3 P rad out =5.5 MW P rad total =23 MW P rad total / P heat SOL =.62 7 MWm -3 High radiation in both inner and outer divertors is predicted H. Kawashima, et al, J Nuc Mater 415 (211) S948.

9 Detachment even w/o Ar seeding for #2 ( cf. Ar seeding mandatory for #5-1 ) Transients: Keep detachment during ELMs Slow transients: Lowering fusion output, lower β, OSP toward outer, pumping changes, plasma changes H. Kawashima, et al, J Nuc Mater 415 (211) S948. Scenario I p (MA) B T (T) R p m a p (m) A κ x δ x.5.47 S q V p (m 3 ) P in (MW) H H β N τ E (s) T i () (kev) T e () (kev) n e () (1 19 /m 3 ) n bar e (1 19 / m 3 ) 6.3 n e / n Greenwald.5.85 f BS τ plasma (s) Z (m) -2.2 Scenario 2 SONIC simulation for Full-Ip & heating plasm With W divertor *preliminary χ e = m 2 /s χ i = m 2 /s D =.3 m 2 /s inner targets S pump : 5 m 3 /s P SOL = 37 MW Γ ion SOL = 2.8 x1 21 s -1 Coronal W + MC Ar (n e τ = 1x1 16 s/m 3 ) R (m) outer targets PFC: W Γ D2 Puff = - x1 22 s MW/m 2 x1 s for 3 cycles 1 MW/m 2 x1 s for 1 cycles

10 4. Analysis of Ar transport by IMPMC code on W-wall Ar transport on W-wall (nw/ni=1e-5 (uniform)) was analyzed by the IMPMC code combined with SONIC. Conditions : Ar puff =.2 Pam3/s, Γp=e22 /s. - Results : qt=9.3 MW/m2, ne-mid=5.7e19 m-3, Prad=2 MW. (run_ _wx38) It closes to the results at case B (n /n =1e-5 (uniform)) of Ar Non-coronal simulation as shown in w i - Conditons : nar/ni =1e-3, Γp = e22 /s Results : qt=1 MW/m2, ne-mid=5.6e19 m-3, Prad=18.6 MW Mar/11/15 - Nz msec 2D profile of ni and Te at IMPMC simulation ni - Nz Nz - 3 Log NAr (x119 m-3) rt Mar/11/ Nz :53: Lower ionized Ar (+1~+7) is distributed SOL/Div. regions. Middle Ar (+8~+15) moves side. ionized to inner Higher ionized Ar (+16~+18) concentrates typically on the bottom of core edge regions. - 2 ZAr(+16~+18) n=1 shell 16:53:52 Nz msec - 1 M w ZAr(+8~+15) n=2 shell D profile of Ar density each ionized charge - Nz Mar/11/ msec Nz ZAr(+1~+7) n=3 shell Nz msec msec 4 - Te (ev) Nz Te 16:53: 2 1 Mar/11/15 16:53: H.#Kawashima,#RCM/4#215/5/19,#to#be#presented#in#PET15.5 m-3) 4 2 Nz Te (119 - Nz z rt1 1.1 E-2 E-2 E-3 E-3 E-4 2 M

11 rt1 - E-2 E-2 E-3 E-3 E-4 E-4 Mar/4/15 - Ni E-2 E-2 Mar/4/15 wxdr_6 17:14:18 Mar/4/15 17:16:48.1 E-2 E-2 E-3 E-3 which is closed E-4 E-4-4~1-3 in the divertor regions, Ar ratio (nar/ni) becomes 1 that for Noncoronal calculation at case B. the leg on high Radiation loss power (Wrad) is enhanced ne and low T along divertor e. Both nar/ni and r Wrad are also enlarged on the bottom of core edge regions. r (m) (m) Ni Profiles on the divertor target heat load qt qt_mc_run_214118_wx34 Qdpl_o._&6_cor qt_nc_run_21529_wx t q (W) separatrix hit point 1 1 IMPMC calc. 3 (Ar_puff=.2 Pam /s) distance from the hit-point Δ (m) # They almost agree with IMPMC and non-coronal evaluations E-2 E-2 Ni msec 17:16:48 Wrad (MW/m3) Wrd 4.1 E-2 E-2 E-3 E-3 E-4 E-4.1-2D profile of nar/ni and Wrad nar/ni

12 Profiles on the density n ed and temperature T ed ned_mc_run_214118_wx34 ned_nc_run_21529_wx6 Nd_Qdpl_o._&6_cor 15 Ted_MC_run_214118_wx34 Ted_nc_run_21529_wx6 Td_Qdpl_o._&6_cor n ed (1 19 m -3 ) separatrix hit point T ed (ev) IMPMC calc. (A r_puff =.2 Pam 3 /s) 1 5 separatrix hit point distance from the hit-point Δ (m) distance from the hit-point Δ (m) # n ed almost agree on the divertor target. # Differences by the calculation method appear on T ed at the outer regions. Long term plan in EUROfusion 24 In EUROfusion, work package "Preparation of JT-6SA exploitation" was started with a comprehensive long-term plan of the three sub-groups Resources (ppy) Modelling Sub-systems Operation (in cooperation with F4E) Training integrated modelling of flat-top integrated modelling of ramp-up/down, transients systematic MHD analysis of scenarios (ideal, resistive, core/pedestal) physics studies: gyrofluid & gyrokinetic simulations, Alfvén instabilities, etc. simulation of control tools ECRH antenna optical tests ECRH antenna control software development divertor pumping computations conceptual design of diagnostics tests conceptual design of matter injection systems tests feasibility study of a W divertor conceptual design of a W divertor development of new data system tests and implementation development and test of analysis tool set development and test of remote participation tools. preliminary tests of remote access Towards a EU remote control room working group on operation write Operation Handbook select and train Session Leaders working group on select Topical campaign management Group Leaders Training JT-6SA generation in view of ITER Overall strategy and main milestones in were agreed in RCM-3 (May 214).

13 Feasibility study of transition to a W divertor in JT-6SA R. Neu 1, G.Ciraolo 2, M. Missirlian 2, R. Stankiewicz 3, W. Stępniewski 3, M. Wischmeier 1, R. Zagórski 3 T. Nakano (JT-6SA R.O.) 1MPI für Plasmaphysik, Garching, Germany 2 CEA, IRFM, Saint-Paul-Lez-Durance, France 3 IPPLM, Warsaw, Poland All Metal PFCs in European Roadmap Options for test of all metal / all W PFCs in preparation of DEMO JET: serious option, but currently not discussed (DT compatible?) JT6-SA: potentially all necessary ingredients available! DTT: net yet decided, potentially too small to achieve relevant scaling with AUG ITER: potentially most relevant experiment, but unclear whether technical feasible, late! JET JT-6 SA DTT Result of ITER main chamber W assessment 4th JT-6SA Research Coordination Meeting W-divertor R. Neu PAGE 26