WEST Physics Basis

Nuclear Fushion

article

C. Bourdelle¹  J.F. Artaud¹  V. Basiuk¹  M. Bécoulet¹  S. Brémond¹  J. Bucalossi¹  H. Bufferand¹  G. Ciraolo¹  L. Colas¹  Y. Corre¹  X. Courtois¹  J. Decker²  L. Delpech¹  P. Devynck¹  G. Dif-Pradalier¹  R.P. Doerner³  D. Douai¹  R. Dumont¹  A. Ekedahl¹  N. Fedorczak¹  C. Fenzi¹  M. Firdaouss¹  J. Garcia¹  P. Ghendrih¹  C. Gil¹  G. Giruzzi¹  M. Goniche¹  C. Grisolia¹  A. Grosman¹  D. Guilhem¹  R. Guirlet¹  J. Gunn¹  P. Hennequin⁴  J. Hillairet¹  T. Hoang¹  F. Imbeaux¹  I. Ivanova-Stanik⁵  E. Joffrin¹  A. Kallenbach⁶  J. Linke⁷  T. Loarer¹  P. Lotte¹  P. Maget¹  Y. Marandet⁸  M.L. Mayoral⁹  O. Meyer¹  M. Missirlian¹  P. Mollard¹  P. Monier-Garbet¹  P. Moreau¹  E. Nardon¹  B. Pégourié¹  Y. Peysson¹  R. Sabot¹  F. Saint-Laurent¹  M. Schneider¹  J.M. Travère¹  E. Tsitrone¹  S. Vartanian¹  L. Vermare⁴  M. Yoshida^1,11  R. Zagorski⁵ 

[1] CEA;Centre de Recherches en Physique des Plasmas;Center for Energy Research, University of California in San Diego;Ecole Polytechnique;Institute of Plasma Physics and Laser Microfusion;Max Planck Institute f. Plasma Physics;Forschungszentrum Jülich;Aix-Marseille Université;CCFE, Culham Science Centre;EUROfusion Programme Management Unit;Japan Atom Energy Agency

关键词: plasma facing components;    divertor;    tokamak;    plasma physics;   

DOI  :  10.1088/0029-5515/55/6/063017

来源: Institute of Physics Publishing Ltd.

【 摘 要 】

With WEST (Tungsten Environment in Steady State Tokamak) (Bucalossiet al2014Fusion Eng. Des. 89907–12 ), the Tore Supra facility and team expertise (Dumontet al2014Plasma Phys. Control. Fusion 56075020 ) is used to pave the way towards ITER divertor procurement and operation. It consists in implementing a divertor configuration and installing ITER-like actively cooled tungsten monoblocks in the Tore Supra tokamak, taking full benefit of its unique long-pulse capability. WEST is a user facility platform, open to all ITER partners. This paper describes the physics basis of WEST: the estimated heat flux on the divertor target, the planned heating schemes, the expected behaviour of the L–H threshold and of the pedestal and the potential W sources. A series of operating scenarios has been modelled, showing that ITER-relevant heat fluxes on the divertor can be achieved in WEST long pulse H-mode plasmas.

【 授权许可】

Unknown