High heat flux testing of tungsten plasma facing materials

被引:11
|
作者
Zhou, Zhang-jian [1 ]
Song, Shu-xiang [1 ]
Du, Juan [1 ]
Ge, Chang-chun [1 ]
机构
[1] Univ Sci & Technol Beijing, Sch Mat Sci & Engn, Res Ctr Fus Mat, Beijing 100083, Peoples R China
基金
中国国家自然科学基金;
关键词
D O I
10.1016/j.jnucmat.2007.04.006
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Both tungsten with a microstructure of ultra-fine grain size (sub-micron grain size) and functionally graded W/Cu materials have been fabricated by a newly developed technology named resistance sintering under ultra-high pressure. It is found that when decreasing the grain size of tungsten (from 7 mu m to 0.5 mu m), the micro-hardness and bend strength of tungsten will increase significantly. Thermal shock resistance by water quenching shows that the concept of functionally graded materials is effective at reducing the thermal stress between tungsten and copper. High heat flux testing using a laser beam shows that tungsten with sub-micron grain size can endure a higher heat load than that of tungsten with a grain size of larger than 1 mu m, and functionally graded W/Cu materials can endure a higher heat load than that of pure tungsten. (c) 2007 Elsevier B.V. All rights reserved.
引用
收藏
页码:1468 / 1471
页数:4
相关论文
共 50 条
  • [1] Development and high heat flux testing of plasma facing materials for future fusion experiments
    Linke, J
    Kapoustina, A
    Pitzer, D
    Rödig, M
    Singheiser, L
    [J]. PRICM 5: THE FIFTH PACIFIC RIM INTERNATIONAL CONFERENCE ON ADVANCED MATERIALS AND PROCESSING, PTS 1-5, 2005, 475-479 : 1361 - 1366
  • [2] Baseline high heat flux and plasma facing materials for fusion
    Ueda, Y.
    Schmid, K.
    Balden, M.
    Coenen, J. W.
    Loewenhoff, Th.
    Ito, A.
    Hasegawa, A.
    Hardie, C.
    Porton, M.
    Gilbert, M.
    [J]. NUCLEAR FUSION, 2017, 57 (09)
  • [3] ITER relevant high heat flux testing on plasma facing surfaces
    Hirai, T
    Ezato, K
    Majerus, P
    [J]. MATERIALS TRANSACTIONS, 2005, 46 (03) : 412 - 424
  • [4] High Heat Flux Testing of Castellated Graphite Plasma Facing Components
    Gray, T. K.
    Youchison, D. L.
    Ellis, R. E.
    Jaworski, M. A.
    Khodak, A.
    Looby, T.
    Reinke, M. L.
    Smalley, G.
    Wolfe, D. E.
    [J]. FUSION SCIENCE AND TECHNOLOGY, 2021, 77 (01) : 9 - 18
  • [5] High heat flux testing of plasma facing materials and components -: Status and perspectives for ITER related activities
    Linke, J.
    Escourbiac, F.
    Mazul, I. V.
    Nygren, R.
    Roedig, M.
    Schlosser, J.
    Suzuki, S.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2007, 367 (SPEC. ISS.) : 1422 - 1431
  • [6] HIGH HEAT-FLUX COMPOSITES FOR PLASMA-FACING MATERIALS
    TING, JM
    LAKE, ML
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1994, 212 : 1141 - 1145
  • [7] Development of advanced high heat flux and plasma-facing materials
    Linsmeier, Ch.
    Rieth, M.
    Aktaa, J.
    Chikada, T.
    Hoffmann, A.
    Hoffmann, J.
    Houben, A.
    Kurishita, H.
    Jin, X.
    Li, M.
    Litnovsky, A.
    Matsuo, S.
    von Mueller, A.
    Nikolic, V.
    Palacios, T.
    Pippan, R.
    Qu, D.
    Reiser, J.
    Riesch, J.
    Shikama, T.
    Stieglitz, R.
    Weber, T.
    Wurster, S.
    You, J. -H.
    Zhou, Z.
    [J]. NUCLEAR FUSION, 2017, 57 (09)
  • [8] Plasma facing and high heat flux materials - needs for ITER and beyond
    Bolt, H
    Barabash, V
    Federici, G
    Linke, J
    Loarte, A
    Roth, J
    Sato, K
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2002, 307 : 43 - 52
  • [9] High heat flux testing of divertor plasma facing materials and components using the HHF test facility at IPR
    Patil, Yashashri
    Khirwadkar, S. S.
    Belsare, Sunil
    Swamy, Rajamannar
    Tripathi, Sudhir
    Bhope, Kedar
    Kanpara, Shailesh
    [J]. PHYSICA SCRIPTA, 2016, T167
  • [10] Overview on fabrication and joining of plasma facing and high heat flux materials for ITER
    Merola, M
    Akiba, M
    Barabash, V
    Mazul, I
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2002, 307 : 1524 - 1532