Overview of the ITER-like wall project

被引:184
|
作者
Matthews, G. F. [1 ]
Edwards, P.
Hirai, T.
Kear, M.
Lioure, A.
Lomas, P.
Loving, A.
Lungu, C.
Maier, H.
Mertens, P.
Neilson, D.
Neu, R.
Pamela, J.
Philipps, V.
Piazza, G.
Riccardo, V.
Rubel, M.
Ruset, C.
Villedieu, E.
Way, M.
机构
[1] UKAEA Euratom Fus Assoc, Culham Sci Ctr, Abingdon, Oxon, England
[2] EURATOM, Forschungszentrum Julich, Julich, Germany
[3] EFDA, Close Support Unit, Culham Sci Ctr, Abingdon, Oxon, England
[4] Assoc Euratom MEdC, Nat Inst Laser Plasma & Radiat Phys, Bucharest, Romania
[5] Max Planck Inst Plasma Phys, EURATOM Assoc, D-85748 Garching, Germany
[6] EFDA, Close Support Unit, D-85748 Garching, Germany
[7] Royal Inst Technol KTH, Assoc EURATOM VR, Alfven Lab, S-10044 Stockholm, Sweden
[8] CEA, EURATOM Assoc, Cadarache, DSM DRFC, St Paul Les Durance, France
[9] EURATOM, TEKES, VTT Proc, Espoo, Finland
[10] ENEA, EURATOM Assoc, Frascati, Italy
[11] CEN SCK, EURATOM Assoc, B-2400 Mol, Belgium
基金
英国工程与自然科学研究理事会;
关键词
D O I
10.1088/0031-8949/2007/T128/027
中图分类号
O4 [物理学];
学科分类号
0702 ;
摘要
Work is in progress to completely replace, in 2008/9, the existing JET CFC tiles with a configuration of plasma facing materials consistent with the ITER design. The ITER-like wall (ILW) will be created with a combination of beryllium ( Be), tungsten ( W), W-coated CFC and Be-coated inconel tiles, with the material depending on the local anticipated heat flux and geometry. It is part of an integrated package of JET enhancements whose aim is to develop an understanding of the ITER materials issues and develop the techniques required to operate with inductive and advanced scenarios as close as possible to ITER parameters. Over 4000 tiles will be replaced and the ILW will accommodate additional heating up to at least 50 MW for 10 s. This paper describes the scientific background to the project, the technical objectives, the material configuration selected, the R&D behind the practical realization of the objectives and the generic problems associated with the Be tiles ( power handling capacity and disruption induced eddy currents). One of the objectives is to maintain or improve the existing CFC tile power handling performance which has been achieved in most cases by hiding bolt holes, optimizing tile size and profile and introducing castellations on plasma facing surfaces.
引用
收藏
页码:137 / 143
页数:7
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