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@ARTICLE{Bourdelle:837692,
author = {Bourdelle, C. and Artaud, J. F. and Basiuk, V. and
Bécoulet, M. and Brémond, S. and Bucalossi, J. and
Bufferand, H. and Ciraolo, G. and Colas, L. and Corre, Y.
and Courtois, X. and Decker, J. and Delpech, L. and Devynck,
P. and Dif-Pradalier, G. and Doerner, R. P. and Douai, D.
and Dumont, R. and Ekedahl, A. and Fedorczak, N. and Fenzi,
C. and Firdaouss, M. and Garcia, J. and Ghendrih, P. and
Gil, C. and Giruzzi, G. and Goniche, M. and Grisolia, C. and
Grosman, A. and Guilhem, D. and Guirlet, R. and Gunn, J. and
Hennequin, P. and Hillairet, J. and Hoang, T. and Imbeaux,
F. and Ivanova-Stanik, I. and Joffrin, E. and Kallenbach, A.
and Linke, J. and Loarer, T. and Lotte, P. and Maget, P. and
Marandet, Y. and Mayoral, M. L. and Meyer, O. and
Missirlian, M. and Mollard, P. and Monier-Garbet, P. and
Moreau, P. and Nardon, E. and Pégourié, B. and Peysson, Y.
and Sabot, R. and Saint-Laurent, F. and Schneider, M. and
Travère, J. M. and Tsitrone, E. and Vartanian, S. and
Vermare, L. and Yoshida, M. and Zagorski, R.},
title = {{WEST} {P}hysics {B}asis},
journal = {Nuclear fusion},
volume = {55},
number = {6},
issn = {1741-4326},
address = {Vienna},
publisher = {IAEA},
reportid = {FZJ-2017-06553},
pages = {063017},
year = {2015},
abstract = {With WEST (Tungsten Environment in Steady State Tokamak)
(Bucalossi et al 2014 Fusion Eng. Des. 89 907–12), the
Tore Supra facility and team expertise (Dumont et al 2014
Plasma Phys. Control. Fusion 56 075020) 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.},
cin = {IEK-2},
ddc = {530},
cid = {I:(DE-Juel1)IEK-2-20101013},
pnm = {174 - Plasma-Wall-Interaction (POF3-174)},
pid = {G:(DE-HGF)POF3-174},
typ = {PUB:(DE-HGF)16},
UT = {WOS:000356236500019},
doi = {10.1088/0029-5515/55/6/063017},
url = {https://juser.fz-juelich.de/record/837692},
}