ITER-Test blanket module functional materials

被引:48
作者
Wong, C. P. C.
Chernov, V.
Kimura, A.
Katoh, Y.
Morley, N.
Muroga, T.
Song, K. W.
Wu, Y. C.
Zmitko, M.
机构
[1] Gen Atom Co, San Diego, CA 92186 USA
[2] AA Bochvar Inorgan Mat Res Inst, Moscow, Russia
[3] Kyoto Univ, Inst Adv Energy, Kyoto, Japan
[4] Oak Ridge Natl Lab, Oak Ridge, TN USA
[5] Univ Calif Los Angeles, Los Angeles, CA USA
[6] Natl Inst Fus Sci, Toki, Japan
[7] Korea Atom Energy Res Inst, Yuseong, South Korea
[8] Inst Plasma Res, Hefei, CAS, Peoples R China
[9] EFDA, Close Support Unit, Garching, Germany
关键词
D O I
10.1016/j.jnucmat.2007.03.241
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Solid breeder and liquid breeder blanket concepts are being developed for testing in ITER. In addition to fundamental investigations on the use of reduced activation ferritic/ferritic-martensitic steels (RAFMS) or V-alloys as the structural material, tritium breeder and neutron multiplier materials, and corresponding corrosion issues, there are three classes of functional materials being developed. Performance of these functional materials will significantly impact the performance of respective blanket concepts. Two classes of materials are related to the self-cooled liquid breeder design concepts. The first class is MHD coatings for the self-cooled Li breeder concepts. The second class is for flow channel inserts (FCI) for the dual coolant PbLi concepts. The third class of functional material is tritium permeation barrier material commonly needed for solid and liquid breeder blanket concepts. A description and the development status of these functional materials are described in this paper. (c) 2007 Elsevier B.V. All rights reserved.
引用
收藏
页码:1287 / 1292
页数:6
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