Emmanuel JoffrinXXth Fusion Energy Conference, November 2004 1 The « hybrid » scenario in JET: towards its validation for ITER E. Joffrin, A. C. C. Sips,

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Presentation transcript:

Emmanuel JoffrinXXth Fusion Energy Conference, November The « hybrid » scenario in JET: towards its validation for ITER E. Joffrin, A. C. C. Sips, J. F. Artaud, A. Becoulet, R. Budny, P. Buratti, P. Belo, C. D. Challis, F. Crisanti, M. de Baar, P. de Vries, C. Gormezano, C. Giroud, O. Gruber, G.T.A. Huysmans, F. Imbeaux, A. Isayama, X. Litaudon, P. J. Lomas, D. C. McDonald, Y. S. Na, S. D. Pinches, A. Staebler, T. Tala, A. Tuccillo, K.-D. Zastrow and JET-EFDA Contributors to the Work Programme. Outline: - Introduction to the hybrid scenario in JET - Physics analysis (MHD, current, transport) - Projections to ITER burning plasma for the hybrid scenario

Emmanuel JoffrinXXth Fusion Energy Conference, November ITER scenario for steady state burning conditions Maximise:  G =  N. H / q 95 2  I boot / I p ~  N. q 95  n ~ 0.85 n Greenwald AUG: A. Staebler EX/4-4 DIII-D: M. Wade EX/4-1 JET has started the study of the « hybrid » regime in the 2003 campaign NTM with sawteeth High Ip disruptions Current control High  MHD Non-inductive RS Hybrid scenario q-profile H-mode inductive scenario Normalised radius

Emmanuel JoffrinXXth Fusion Energy Conference, November JET hybrid regime (1.7T, 1.4MA) Identity experiment with ASDEX Upgrade: 1.Matched magnetic configurations. 2.Similar  * & q (q o ~1 and q 95 =4). B o  IPB98(y,2)   *   * q -3.0  0.73   N controlled in real time with P IN 4. *(JET)=0.08  *(AUG) = 0.15 Hybrid scenario reproduced in JET with similar phenomenology than in AUG.

Emmanuel JoffrinXXth Fusion Energy Conference, November Hybrid regimes in JET JET can bridge the gap between machines like ASDEX Upgrade and ITER The hybrid regime has been achieved in JET: with AUG configuration  =0.45 with ITER configuration  =0.45 at 2.4T (lower  *) and  =0.22 at 2.4T (lower  *) and  =0.45 Development of the hybrid regime towards the ITER domain With more available power, future experiments are planning to explore the low  * region reachable by ITER JET-AUG Identiy

Emmanuel JoffrinXXth Fusion Energy Conference, November /1 NTM Sawteeth Pulse & NTM control in hybrid regime Benign NTMs in main heating phase at high  N W island ~3-4cm  impact on confinement ~5% In JET, NTM are avoided by tuning the target q profile above 1 in the preheat phase In JET, the hybrid scenario can operate at  N >2.5 with moderate NTM activity as in other devices (ASDEX Upgrade & DIII-D) 1/1 mode & fishbones 4/3 mode 3/2 mode

Emmanuel JoffrinXXth Fusion Energy Conference, November q(0)=1.07  p =1.25 q(0)=1.07  p =1.25 m=1 m=3 m=2 Ideal MHD in hybrid regime JET has reached ~95% of the ideal kink limit so far.  Ideal m=1 kink mode behaviour predicted in JET using MISHKA code. Strong increase of the ideal kink growth rate as plasma pressure increases. Also suggests that control of the q profile is necessary to keep q away from unity Mode localisation

Emmanuel JoffrinXXth Fusion Energy Conference, November Current balance in the hybrid regime I NBCD / I p =35%; I boot / I p =25% Current diffusion analysis with the CRONOS code At  N =2.8, non-inductive current sources are sufficient to maintain a steady state q profile J TOT [MA/mJ TOT [MA/m 2 ] J NBCD 2 J [MA/m] 2 J BOOT [MA/m 2 ] J BOOT Pulse 58323,  N =2.8From TRANSP Normalised radius

Emmanuel JoffrinXXth Fusion Energy Conference, November Confinement in the hybrid regime (Cordey et al., IT/P3-32 In JET at high  N hybrid regime have an improved confinement of up to 20 % with respect to IPB98y2. IPB98(y,2):  *  * q -3.0 Recent dedicated studies have shown that confinement has a weaker negative dependence on  At high  N, he higher confinement observed in hybrid regime could be related to the  dependence of the IPB98(y,2) scaling Pure gyro-Bohm Pure gyro-Bohm scaling:  * -3  0 * -0.1 q -1.7 Gives a reasonable fit to the data. & McDonald, EX/6-6)

Emmanuel JoffrinXXth Fusion Energy Conference, November Comparative transport property of the hybrid regime 1.As expected, ITB discharges are showing ion temperature gradients well above the predicted critical gradients for ITGs 2.Hybrid scenario are behaving in the same way as the standard ELMy H- mode. Supported by turbulence measurements with reflectometry. In JET, it appears that the confinement in hybrid regimes is not significantly different than in the standard ELMy H-mode scenario. 15 For s>0.2 & R/L n < ITB regime ELMy H-mode Hybrid regime R/L Ti critical from theory R/L Ti (exp) (Jenko et al., PoP, 2002)

Emmanuel JoffrinXXth Fusion Energy Conference, November Tritium and impurity transport D [m 2 /s] V [m/s] Pulse (  N =2.7) D neo [m 2 /s] Normalised radius V neo [m/s] Tritium and impurity diffusion and convection in hybrid regime are dominated by turbulent transport. (D. Stork, OV/4-1 & McDonald, EX/6-6) Tritium NormalisedradiusNormalisedradius (B T =2.4T;  =0.45) (B T =2.4T;  =0.20) Neoclassical D [m 2 /s] V [m/s] (B T =2.4T;  =0.45) (B T =2.4T;  =0.20) Neoclassical D [m 2 /s] V [m/s] Neon (Z=10) Particle and impurity diffusion and convection inferred from the SANCO + UTC codes constrained by experimental data Trace tritium injection ( Neutron monitor + fit )

Emmanuel JoffrinXXth Fusion Energy Conference, November ITER projections with the hybrid scenario Scaling used P fus [MW] P aux [MW] NN Density peaking Q fus q 95 Ip [MA] Projections for burning hybrid regime in ITER with the integrated 1D code CRONOS Hypothesis: - HH=1 - Gyro-Bohm transport normalised to scaling laws. - Pedestal height from pedestal database scaling law. - Zeff=1.8, He concentration 3% Reaching high  N requires the fine tuning of plasma current IPB98y2 (PPA) IPB98y Comparison with PPA IPB98y Pure Gyro-Bohm Scaling comparison Pure Gyro-Bohm ne o =1.5 x ne ped With ne peaking Pure Gyro-Bohm ne o =1.5 x ne ped Lower q 95

Emmanuel JoffrinXXth Fusion Energy Conference, November Conclusions 1.The steady state “hybrid” scenario has been successfully reproduced in JET by the mean of an identity experiment approach with ASDEX-Upgrade. 2.In JET, current control is a key factor in avoiding NTM activity during the main heating phase of the scenario. 3.The JET hybrid scenario does not show any obvious sign of improved heat and particle confinement with respect to standard ELMy H-modes. On the other hand, its improved stability allows operation at higher  N close to the ideal limit. 4.The maximisation of confinement and stability properties provides to the hybrid regime a good probability for achieving high fusion gain at reduced current (~13MA) for more than 2000s.

Emmanuel JoffrinXXth Fusion Energy Conference, November Performance overview towards ITER Bootstrap fraction from TRANSP data (q 95 =4) JET Hybrid regime are situated in the right ball park in terms of Ti/Te, density and plasma performance

Emmanuel JoffrinXXth Fusion Energy Conference, November /1 mode & fishbones Spectrogram of magnetic fluctuations NTM in hybrid regime 4/3 mode 3/2 mode Coupled Islands size is 3 to 4cm located at r/a= Limited impact on global confinement few percent In JET, the hybrid scenario can operate at  N >2.5 with moderate NTM activity as in other devices (ASDEX Upgrade & DIII-D) Neoclassical tearing mode behaviour in the hybrid regime 1 < q < 1.3 in plasma core ELMs ~40Hz

Emmanuel JoffrinXXth Fusion Energy Conference, November Summary of advanced modes development ITER (PPA Q=5.4, T burn =1000s):  = 0.48 q 95 =3.5 f GW =0.85 H=1  N =1.9 f BS =17% ITER (Q=5 Steady State):  =0.49 q 95 =5.5 f GW =0.8 H=1.5  N =3 f BS =50% Hybrid Mode or improved H-mode (new on JET) Plasmas with ITBs