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ITER-Test blanket module functional materials

  • C. P.C. Wong
  • , V. Chernov
  • , A. Kimura
  • , Y. Katoh
  • , N. Morley
  • , T. Muroga
  • , K. W. Song
  • , Y. C. Wu
  • , M. Zmitko
  • General Atomics
  • All-Russian Scientific Research Institute of Inorganic Materials
  • Kyoto University
  • Oak Ridge National Laboratory
  • University of California at Los Angeles
  • National Institute for Fusion Science
  • Korea Atomic Energy Research Institute
  • European Fusion Development Agreement

科研成果: 期刊稿件 › 文章 › 同行评审

60 引用 (Scopus)

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.

源语言英语
页(从-至)1287-1292
页数6
期刊Journal of Nuclear Materials
卷367-370 B
期SPEC. ISS.
DOI
出版状态已出版 - 1 8月 2007

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