The WEST programme: Minimizing technology and operational risks of a full actively cooled tungsten divertor on ITER

被引：24

作者：

Grosman, Andre ^{[1
]}

Bucalossi, Jerome ^{[1
]}

Doceul, Louis ^{[1
]}

Escourbiac, Frederic ^{[2
]}

Lipa, Manfred ^{[1
]}

Merola, Mario ^{[2
]}

Missirlian, Marc ^{[1
]}

Pitts, Richard A. ^{[2
]}

Samaille, Franck ^{[1
]}

Tsitrone, Emmanuelle ^{[1
]}

机构：

[1] CEA, IRFM, F-13108 St Paul Les Durance, France

[2] ITER Org, F-13115 St Paul Les Durance, France

来源：

FUSION ENGINEERING AND DESIGN | 2013年 / 88卷 / 6-8期

关键词：

ITER; Tore Supra; WEST; Tungsten; Divertor; Plasma-facing components; PLASMA-FACING COMPONENTS; TORE-SUPRA; QUALIFICATION;

D O I：

10.1016/j.fusengdes.2013.02.039

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

The WEST programme consists in transforming the Tore Supra tokamak into an X point divertor device, while taking advantage of its long discharge capability. This is obtained by inserting in vessel coils to create the X point while adapting the in-vessel elements to this new geometry. This will allow the full tungsten divertor technology to be used on ITER to be tested in anticipation of its use on ITER under relevant heat loading conditions and pulse duration. The early manufacturing of a significant industrial series of ITER-similar W plasma-facing units will contribute to the ITER divertor manufacturing risk mitigation and to that associated with early W divertor plasma operation on ITER. (C) 2013 Elsevier B.V. All rights reserved.

引用

页码：497 / 500

页数：4

共 10 条

[1] Feasibility study of an actively cooled tungsten divertor in Tore Supra for ITER technology testing [J].

Bucalossi, J. ;

Argouarch, A. ;

Basiuk, V. ;

Baulaigue, O. ;

Bayetti, P. ;

Becoulet, M. ;

Bertrand, B. ;

Bremond, S. ;

Cara, P. ;

Chantant, M. ;

Corre, Y. ;

Courtois, X. ;

Doceul, L. ;

Ekedahl, A. ;

Faisse, F. ;

Firdaouss, M. ;

Garcia, J. ;

Gargiulo, L. ;

Gil, C. ;

Grisolia, C. ;

Gunn, J. ;

Hacquin, S. ;

Hertout, P. ;

Huysmans, G. ;

Imbeaux, F. ;

Jiolat, G. ;

Joanny, M. ;

Jourd'heuil, L. ;

Jouve, M. ;

Kukushkin, A. ;

Lipa, M. ;

Lisgo, S. ;

Loarer, T. ;

Maget, P. ;

Magne, R. ;

Marandet, Y. ;

Martinez, A. ;

Mazon, D. ;

Meyer, O. ;

Missirlian, M. ;

Monier-Garbet, P. ;

Moreau, P. ;

Nardon, E. ;

Panayotis, S. ;

Pegourie, B. ;

Pitts, R. A. ;

Portafaix, C. ;

Richou, M. ;

Sabot, R. ;

Saille, A. .

FUSION ENGINEERING AND DESIGN, 2011, 86 (6-8) :684-688

[2] Design, integration and feasibility studies of the Tore-Supra West divertor structure [J].

Doceul, L. ;

Bucalossi, J. ;

Larroque, S. ;

Lipa, M. ;

Portafaix, C. ;

Saille, A. ;

Samaille, F. ;

Soler, B. ;

Ferlay, F. ;

Verger, J. M. .

FUSION ENGINEERING AND DESIGN, 2013, 88 (6-8) :814-817

[3] Validation of the ITER-relevant passive-active-multijunction LHCD launcher on long pulses in Tore Supra [J].

Ekedahl, A. ;

Delpech, L. ;

Goniche, M. ;

Guilhem, D. ;

Hillairet, J. ;

Preynas, M. ;

Sharma, P. K. ;

Achard, J. ;

Bae, Y. S. ;

Bai, X. ;

Balorin, C. ;

Baranov, Y. ;

Basiuk, V. ;

Becoulet, A. ;

Belo, J. ;

Berger-By, G. ;

Bremond, S. ;

Castaldo, C. ;

Ceccuzzi, S. ;

Cesario, R. ;

Corbel, E. ;

Courtois, X. ;

Decker, J. ;

Delmas, E. ;

Ding, X. ;

Douai, D. ;

Goletto, C. ;

Gunn, J. P. ;

Hertout, P. ;

Hoang, G. T. ;

Imbeaux, F. ;

Kirov, K. K. ;

Litaudon, X. ;

Magne, R. ;

Mailloux, J. ;

Mazon, D. ;

Mirizzi, F. ;

Mollard, P. ;

Moreau, P. ;

Oosako, T. ;

Petrzilka, V. ;

Peysson, Y. ;

Poli, S. ;

Prou, M. ;

Saint-Laurent, F. ;

Samaille, F. ;

Saoutic, B. .

NUCLEAR FUSION, 2010, 50 (11)

[4] Qualification, commissioning and in situ monitoring of high heat flux plasma facing components [J].

Escourbia, F. ;

Durocher, A. ;

Grosman, A. ;

Cismondi, F. ;

Courtois, X. ;

Farjon, J. L. ;

Schlosser, J. ;

Merola, M. ;

Tivey, R. .

FUSION ENGINEERING AND DESIGN, 2007, 82 (15-24) :1730-1738

[5] High heat flux actively cooled plasma facing components development, realisation and first results in Tore Supra [J].

Grosman, A .

FUSION ENGINEERING AND DESIGN, 2005, 74 (1-4) :49-57

[6]

Larroque S., 2013, FUSION ENG DESIGN, DOI DOI 10.1016/J.FUSENGDES.2013.01.015

[7] DEVELOPMENT OF ACTIVELY COOLED PLASMA-FACING COMPONENTS FOR TORE SUPRA [J].

Lipa, M. ;

Schlosser, J. ;

Escourbiac, F. .

FUSION SCIENCE AND TECHNOLOGY, 2009, 56 (03) :1124-1149

[8] Qualification of high heat flux components: application to target elements of W7-X divertor [J].

Missirlian, M. ;

Durocher, A. ;

Grosman, A. ;

Schlosser, J. ;

Boscary, J. ;

Escourbiac, F. ;

Cismondi, F. .

PHYSICA SCRIPTA, 2007, T128 :182-188

[9]

Missirlian M., 2011, PHYS SCRIPTA, VT145

[10] A full tungsten divertor for ITER: Physics issues and design status [J].

Pitts, R. A. ;

Carpentier, S. ;

Escourbiac, F. ;

Hirai, T. ;

Komarov, V. ;

Lisgo, S. ;

Kukushkin, A. S. ;

Loarte, A. ;

Merola, M. ;

Naik, A. Sashala ;

Mitteau, R. ;

Sugihara, M. ;

Bazylev, B. ;

Stangeby, P. C. .

JOURNAL OF NUCLEAR MATERIALS, 2013, 438 :S48-S56

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