5.材料の有する限界と今後の展望 : 5.1構造材料(<特集>実用炉の成立と材料技術II)
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概要
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Candidate structural materials for fusion reactors have been examined from the points of their potentiality and limitation. Austenitic stainless steels, Ieading candidate materials for experimental reactors, have fully matured as engineering materials and have sufficient data for design and construction including irradiation behavior, although the degradation due to irradiation may request re-examination of the conventional design codes. Ferritic steels with some limitation in high temperature strength and irradiation embrittlement are one of the candidate materials for the DEMO reactors and beyond. Advanced materials of vanadium alloys, ceramics and their composites and intermetallic compounds have attractive potentiality in future but they are still laboratory materials and then, much effort for developing is requested. Anyway, to get knowledge and wisdom for using brittle-1ike materiels is essential for fusion reactor development.
- 社団法人プラズマ・核融合学会の論文
- 1994-07-25
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