An ITER-like wall for JET

被引:101
作者
Pamela, J.
Matthews, G. F.
Philipps, V.
Kamendje, R.
机构
[1] Graz Univ Technol, Inst Theoret Phys & Computat Phys, A-8010 Graz, Austria
[2] EFDA, JET, Culham Sci Ctr, Abingdon OX14 3EA, Oxon, England
[3] UKAEA Euratom Fus Assoc, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
[4] EURATOM, Forschungszentrum Julich GmbH, Inst Plasmaphys, D-52425 Julich, Germany
关键词
JET; first wall; divertor material; beryllium; tungsten;
D O I
10.1016/j.jnucmat.2006.12.056
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
This article presents an overview of the new ITER-like wall project in JET. It aims at an optimal use of JET's unique features: physical size, plasma parameters most closely to ITER and the capability to handle beryllium and tritium, allowing the study of critical questions related to operating within the limits of the ITER wall materials. A full replacement of the first wall materials is planned (beryllium in the main wall and tungsten in the divertor). This should deliver answers to urgent plasma surface interaction questions such as tritium retention and provide operational experience in steady and transient conditions with ITER wall materials under relevant geometry and relevant plasma parameters. In addition, the JET auxiliary heating power will be upgraded to similar to 45 MW, allowing access to ITER-relevant disruption and edge localised modes energy loss densities. This will open access to conditions of melt layer formation both on the beryllium first wall and the tungsten divertor. (c) 2007 Elsevier B.V. All rights reserved.
引用
收藏
页码:1 / 11
页数:11
相关论文
共 29 条
[1]  
[Anonymous], 2002, ITER TECHNICAL BASIS
[2]  
BALDWIN MJ, J NUCL MATER, DOI DOI 10.1016/J9JNUCMAT.2007.01.151
[3]   Material erosion at the vessel walls of future fusion devices [J].
Behrisch, R ;
Federici, G ;
Kukushkin, A ;
Reiter, D .
JOURNAL OF NUCLEAR MATERIALS, 2003, 313 :388-392
[4]   Tungsten erosion at the ICRH limiters in ASDEX upgrade [J].
Dux, R. ;
Bobkov, V. ;
Fedorczak, N. ;
Iraschko, K. ;
Kallenbach, A. ;
Neu, R. ;
Puetterich, T. ;
Rohde, V. .
JOURNAL OF NUCLEAR MATERIALS, 2007, 363 :112-116
[5]   Power deposition onto plasma facing components in poloidal divertor tokamaks during type-I ELMS and disruptions [J].
Eich, T ;
Herrmann, A ;
Pautasso, G ;
Andrew, P ;
Asakura, N ;
Boedo, JA ;
Corre, Y ;
Fenstermacher, ME ;
Fuchs, JC ;
Fundamenski, W ;
Federici, G ;
Gauthier, E ;
Goncalves, B ;
Gruber, O ;
Kirk, A ;
Leonard, AW ;
Loarte, A ;
Matthews, GF ;
Neuhauser, J ;
Pitts, RA ;
Riccardo, V ;
Silva, C .
JOURNAL OF NUCLEAR MATERIALS, 2005, 337 (1-3) :669-676
[6]   Nonaxisymmetric energy deposition pattern on ASDEX upgrade divertor target plates during type-I edge-localized modes [J].
Eich, T ;
Herrmann, A ;
Neuhauser, J .
PHYSICAL REVIEW LETTERS, 2003, 91 (19)
[7]   Key ITER plasma edge and plasma-material interaction issues [J].
Federici, G ;
Andrew, P ;
Barabaschi, P ;
Brooks, J ;
Doerner, R ;
Geier, A ;
Herrmann, A ;
Janeschitz, G ;
Krieger, K ;
Kukushkin, A ;
Loarte, A ;
Neu, R ;
Saibene, G ;
Shimada, M ;
Strohmayer, G ;
Sugihara, M .
JOURNAL OF NUCLEAR MATERIALS, 2003, 313 :11-22
[8]   Assessment of erosion of the ITER divertor targets during type I ELMs [J].
Federici, G ;
Loarte, A ;
Strohmayer, G .
PLASMA PHYSICS AND CONTROLLED FUSION, 2003, 45 (09) :1523-1547
[9]   Boundary plasma energy transport in JET ELMy H-modes [J].
Fundamenski, W ;
Sipilä, S .
NUCLEAR FUSION, 2004, 44 (01) :20-32
[10]   Radial propagation of type-I ELMs on JET [J].
Fundamenski, W ;
Sailer, W .
PLASMA PHYSICS AND CONTROLLED FUSION, 2004, 46 (01) :233-259