First scenario development with the JET new ITER-like wall

In the recent JET experimental campaigns with the new ITER-like wall (JET-ILW), major progress has been achieved in the characterization and operation of the H-mode regime in metallic environments: (i) plasma breakdown has been achieved at the first attempt and X-point L-mode operation recovered in a few days of operation; (ii) stationary and stable type-I ELMy H-modes with beta(N) similar to 1.4 have been achieved in low and high triangularity ITER-like shape plasmas and are showing that their operational domain at H = 1 is significantly reduced with the JET-ILW mainly because of the need to inject a large amount of gas (above 10(22) Ds(-1)) to control core radiation; (iii) in contrast, the hybrid H-mode scenario has reached an H factor of 1.2-1.3 at beta(N) of 3 for 2-3 s; and, (iv) in comparison to carbon equivalent discharges, total radiation is similar but the edge radiation is lower and Z(eff) of the order of 1.3-1.4. Strong core radiation peaking is observed in H-mode discharges at a low gas fuelling rate (i. e. below 0.5 x 10(22) Ds(-1)) and low ELM frequency (typically less than 10 Hz), even when the tungsten influx from the diverter is constant. High-Z impurity transport from the plasma edge to the core appears to be the dominant factor to explain these observations. This paper reviews the major physics and operational achievements and challenges that an ITER-like wall configuration has to face to produce stable plasma scenarios with maximized performance.

[1]  M. Lehnen,et al.  Impact and mitigation of disruptions with the ITER-like wall in JET , 2013 .

[2]  A. Loarte,et al.  Improved performance of ELMy H-modes at high density by plasma shaping in JET , 2002 .

[3]  D. A. Humphreys,et al.  ITER startup studies in the DIII-D tokamak , 2008 .

[4]  M. Beurskens,et al.  Impact of carbon and tungsten as divertor materials on the scrape-off layer conditions in JET , 2013 .

[5]  G. Saibene,et al.  Confinement and edge studies towards low ρ* and ν* at JET , 2013 .

[6]  Jet Efda Contributors,et al.  Use of the disruption mitigation valve in closed loop for routine protection at JET , 2013 .

[7]  E. Joffrin,et al.  Characterisation of plasma breakdown at JET with a carbon and ITER-like wall , 2013 .

[8]  J. Contributors,et al.  Impact of the ITER-like wall on divertor detachment and on the density limit in the JET tokamak , 2013 .

[9]  T. Fujita,et al.  Multi-machine transport analysis of hybrid discharges from the ITPA profile database , 2005 .

[10]  R. Budny,et al.  The ‘hybrid’ scenario in JET: towards its validation for ITER , 2005 .

[11]  S. J. Wukitch,et al.  High confinement/high radiated power H-mode experiments in Alcator C-Mod and consequences for International Thermonuclear Experimental Reactor (ITER) QDT = 10 operationa) , 2011 .

[12]  C. Giroud,et al.  Scaling of density peaking in H-mode plasmas based on a combined database of AUG and JET observations , 2007 .

[13]  R. Neu,et al.  Tungsten divertor erosion in all metal devices: Lessons from the ITER like wall of JET , 2013 .

[14]  R. Neu,et al.  The impact of the ITER-like wall at JET on disruptions , 2012 .

[15]  B. Lipschultz Operation of Alcator C-Mod with high-Z plasma facing components and implications , 2005 .

[16]  R. Neu,et al.  The tungsten experiment in ASDEX Upgrade , 1997 .

[17]  S. Brezinsek,et al.  Beryllium migration and evolution of first wall surface composition in the JET ILW configuration , 2013 .

[18]  R. Dux,et al.  ELM flushing and impurity transport in the H-mode edge barrier in ASDEX Upgrade , 2011 .

[19]  J. Contributors,et al.  Metal impurity transport control in JET H-mode plasmas with central ion cyclotron radiofrequency power injection , 2011 .

[20]  Tomonori Takizuka,et al.  Power requirement for accessing the H-mode in ITER , 2008 .

[21]  J. Contributors,et al.  Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER , 2013 .

[22]  C. Giroud,et al.  Improved confinement in JET hybrid discharges , 2012 .

[23]  J. Contributors,et al.  Wall conditioning of JET with the ITER-Like Wall , 2013 .

[24]  R. Felton,et al.  Fuel retention studies with the ITER-Like Wall in JET , 2013 .

[25]  A. Portas,et al.  Present status of the TJ-II remote participation system , 2005 .