Development in DIII D Tokamak Hybrid Operation Scenarios

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1 Development in Tokamak Hybrid Operation Scenarios by R.J. Jayakumar in collaboration with M.R. Wade, T.C. Luce, P.A. Politzer, A.W. Hyatt, J.R. Ferron, C.M. Greenfield, E.H. Joffrin, M. Murakami, C.C. Petty, R. Prater, J.C. DeBoo, R.J. La Haye, P. Gohil, T.L. Rhodes, and A.C.C. Sips Lawrence Livermore National Laboratory Oak Ridge National Laboratory General Atomics CEA Cadarache Euratom Association University of California-Los Angeles Max-Planck-Institut für Plasmaphysik Presented at 6th Annual Meeting American Physical Society Division of Plasma Physics Savannah, Georgia November 9, 99-/RJJ/rs

2 HYBRID REGIME: A NEW STANDARD IN STATIONARY TOKAMAK PERFORMANCE THAT OFFERS ENHANCED RESEARCH OPPORTUNITIES IN ITER 'Hybrid' Regime was originally conceived to take advantage of improved performance and current drive capabilities to achieve long-pulse operation in ITER (at Q fus < ) Over the past few years, has demonstrated stationary operation with β 8% βno-wall and H 89 > over a wide range in q 9 (.8 < q 9 < ) and density (. < n eo /n GW <.7) Projections based on this data are uniformly positive and offer a wide range of operating options in ITER Q fus = (q 9 = ) Q fus = for 9 s (q 9 =.) times Neutron Fluence to enhance materials testing capability 99-/RJJ/rs

3 RECENT EXPERIMENTS HAVE DEMONSTRATED TRULY STATIONARY (> 9 τ R ), HIGH PERFORMANCE OPERATION. I P (MA) P NBI (MW/) (G).... n = B rms n = B rms τ E H 98y τ R H Time (s) β N n e ( 9 m ) Z eff (ρ =.) β T D α β T % β N.7 H 89P =. H 98y =. Z eff =. 99-/RJJ/rs

4 NORMALIZED FUSION PERFORMANCE AND DURATION COMFORTABLY MATCH OR EXCEED ITER BASELINE SCENARIO Fusion Performance: G = β N H 89 /q 9 as measure of P α /P LOSS..8 Duration: N τr = t dur /τ R as measure of stationarity q 9 < q 9 > G.6. ITER Baseline Scenario Target.. N τr 6 8 [Mikkelsen, Phys. Fluids B (989)] 99-/RJJ/rs

5 ... q_9... FUSION PERFORMANCE MAXIMIZES AT LOW q9; G G ITER AT q 9 =. β N..... ITER Baseline Sawteeth H 89 H 98y No Sawteeth ITER Baseline q ITER Baseline ITPA Joint Experiment G = β N H 89 /q q 9... All discharges are at stationary (t>τ R ) β limit mostly due to NTM 99-/RJJ/rs

6 FUSION PERFORMANCE WEAKLY DEPENDENT ON PLASMA DENSITY β N q 9 =. q 9 =..8 G = β N H 89 /q 9 ITER Baseline.6.. ITER Baseline. H 89 {.... H 98y { ITER Baseline n e /n GW n e /n GW All discharges are at stationary (t dur >τ R ) ITPA Joint Experiment No Wall β limited to <β N or / NTM limit 99-/RJJ/rs

7 No / mode With / mode STUDIES HAVE SHOWN / NTM AMPLITUDE IS KEY TO AVOIDANCE OF SAWTEETH n = B rms (G) n = B rms (G)... Time (s) Sawteeth /MW/jy

8 No / mode With / mode Co-ECCD suppresses / mode STUDIES HAVE SHOWN / NTM AMPLITUDE IS KEY TO AVOIDANCE OF SAWTEETH n = B rms (G) EC On... Time (s) n = B rms (G) Sawteeth Sawteeth q ().... Co ECCD.9... Before ECCD W / (m) /MW/jy

9 No / mode With / mode Co-ECCD suppresses / mode Ctr-ECCD enhances / mode STUDIES HAVE SHOWN / NTM AMPLITUDE IS KEY TO AVOIDANCE OF SAWTEETH n = B rms (G) EC On EC On n = B rms (G)... Time (s) Sawteeth Sawteeth q ().... Co ECCD.9... Before ECCD W / (m) Counter ECCD /MW/jy

10 ... NormalizedRadius IMPROVED CONFINEMENT IS DUE TO GOOD TRANSPORT ACROSS ENTIRE PROFILE ( 9 m ) (kev) (kev) Normalized Radius n e T e T i (m /s) χ eff χ i χ e Normalized Radius Leads to broad pressure profile which is favorable for high β limit 6-/MW/jy

11 PROJECTIONS TO ITER ARE UNIFORMLY FAVORABLE AND SUGGESTS IGNITION IS POSSIBLE Projections q 9 =. q 9 =. Plasma current Duration Scaling P fusion Q fus H MA 9 H 98y MA 9 * H H 98y 7 9 * H DS 7 H DS 7 Petty, Fusion Sci. Tech. () Primary difference is β scaling: H 89 : β. H 98y : β.9 H DS : β Projection Methodology: Use plasma shape, q9, and β N, and Hxx from experiment / D-T mix, Z eff prescription from ITER, He ash treated self consistently Use n e, T e profiles, fix T e = T i Choose n/n GW =.8; τ He * / τ E = ; C EJIMA =.6 * 6-/MW/jy

12 Stationary, high normalized performance operation has been demonstrated on over a wide range in operating space. q 9 =.: G = β N H 89 /q 9 >. G ITER for > 9 τ R q 9 =.: G G ITER for > τ R SUMMARY Projections are uniformly favorable for ITER and suggest the possibility of very high fusion gain (possibly Q fus = ) operation as well as long pulse, Q fus > operation in ITER Stability and confinement characteristics are similar to that of the conventional, ELMing H-mode case (ITER physics basis is still valid) Measurements indicate the importance of a small m=/n= NTM in controlling the current profile to prevent or minimize sawteeth, thereby allowing high β, good confinement operation 6-/jy

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