学术探索
学术期刊
新闻热点
数据分析
智能评审

R&D on full tungsten divertor and beryllium wall for JET ITER-like wall project

被引：65
作者：
Hirai, T. [1 ]
Maier, H.
Rubel, M.
Mertens, Ph.
Neu, R.
Gauthier, E.
Likonen, J.
Lungu, C.
Maddaluno, G.
Matthews, G. F.
Mitteau, R.
Neubauer, O
Piazza, G.
Philipps, V.
Riccardi, B.
Ruset, C.
Uytdenhouwen, I.
机构：
[1] EURATOM, Forschungszentrum, Julich, Germany
[2] Max Planck Inst Plasma Phys, EURATOM Assoc, D-85748 Garching, Germany
[3] EURATOM, Royal Inst Technol, Stockholm, Sweden
[4] EURATOM, CEA, DSM, DRFC, St Paul Les Durance, France
[5] EURATOM, VTT, Espoo, Finland
[6] EURATOM, MEdC, Natl Inst Laser Plasma & Radiat Phys, Bucharest, Romania
[7] EURATOM, ENEA, Frascati, Italy
[8] EURATOM, UKAEA, Culham Sci Ctr, Abingdon, Oxon, England
[9] EFDA, Culham Sci Ctr, Close Support Unit, Abingdon, Oxon, England
[10] CEN SCK, Belgian Nucl Res Ctr, B-2400 Mol, Belgium
[11] Univ Ghent, B-9000 Ghent, Belgium
来源：
FUSION ENGINEERING AND DESIGN | 2007年 / 82卷 / 15-24期
基金：
欧盟地平线“2020”;
关键词：
tungsten; beryllium; CFC; coating; JET; ITER; plasma-facing materials; high heat flux test;
D O I：
10.1016/j.fusengdes.2007.02.024
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 ITER reference materials have been tested separately in tokamaks, plasma simulators, ion beams and high heat flux test beds. In order to perform a fully integrated material test JET has launched the ITER-like Wall Project with the aim of installing a full metal wall during the next major shutdown. As a result of R&D projects in 2005-2006, bulk tungsten tiles are foreseen at the outer horizontal target and tungsten coating at the other divertor tiles. In some regions of the main chamber, beryllium coated Inconel tiles and bulk beryllium tiles are utilised which include marker tiles as erosion diagnostics. This paper gives an overview of the R&D carried out in the frame of the ITER-like Wall Project on the development of an inertially cooled bulk tungsten tile design and the characterization of tungsten and beryllium coating technologies. (C) 2007 Elsevier B.V. All rights reserved.
引用
收藏
页码：1839 / 1845
页数：7
相关论文
共 24 条
[11]   Development of tungsten coatings for application in fusion experiments [J].
Maier, H .
PRICM 5: THE FIFTH PACIFIC RIM INTERNATIONAL CONFERENCE ON ADVANCED MATERIALS AND PROCESSING, PTS 1-5, 2005, 475-479 :1377-1382
[12]   Properties of tungsten coatings deposited onto fine grain graphite by different methods [J].
Maier, H ;
Luthin, J ;
Balden, M ;
Linke, J ;
Koch, F ;
Bolt, H .
SURFACE & COATINGS TECHNOLOGY, 2001, 142 :733-737
[13]  
MAIER H, IN PRESS J NUCL MAT
[14]   The new electron beam test facility JUDITH II for high heat flux experiments on plasma facing components [J].
Majerus, P ;
Duwe, R ;
Hirai, T ;
Kühnlein, W ;
Linke, J ;
Rödig, M .
FUSION ENGINEERING AND DESIGN, 2005, 75-79 :365-369
[15]  
MERTENS P, 2006, P ANN M NUCL TECHN A
[16]   Conceptual design for a bulk tungsten divertor tile in JET [J].
Mertens, Ph. ;
Hirai, T. ;
Linke, J. ;
Neubauer, I. ;
Pintsuk, G. ;
Philipps, V. ;
Sadakov, S. ;
Samm, U. ;
Schweer, B. .
FUSION ENGINEERING AND DESIGN, 2007, 82 (15-24) :1833-1838
[17]   Investigation of tungsten coatings on graphite and CFC [J].
Neu, R. ;
Maier, H. ;
Gauthier, E. ;
Greuner, H. ;
Hirai, T. ;
Hopf, Ch ;
Likonen, J. ;
Maddaluno, G. ;
Matthews, G. F. ;
Mitteau, R. ;
Philipps, V. ;
Piazza, G. ;
Ruset, C. .
PHYSICA SCRIPTA, 2007, T128 :150-156
[18]   An ITER-like wall for JET [J].
Pamela, J. ;
Matthews, G. F. ;
Philipps, V. ;
Kamendje, R. .
JOURNAL OF NUCLEAR MATERIALS, 2007, 363 (1-3) :1-11
[19]   Overview of tracer techniques in studies of material erosion re-depostion and fuel inventory in tokamaks [J].
Rubel, MJ ;
Coad, JP ;
Stenström, K ;
Wienhold, P ;
Likonen, J ;
Matthews, GF ;
Philipps, V .
JOURNAL OF NUCLEAR MATERIALS, 2004, 329 :795-799
[20]   Tungsten coatings deposited on CFC tiles by the combined magnetron sputtering and ion implantation technique [J].
Ruset, C. ;
Grigore, E. ;
Maier, H. ;
Neu, R. ;
Li, X. ;
Dong, H. ;
Mitteau, R. ;
Courtois, X. .
PHYSICA SCRIPTA, 2007, T128 :171-174
123