日本原子力学会誌
Online ISSN : 2186-5256
Print ISSN : 0004-7120
高速増殖炉用鋼材の高温ナトリウム中における適合性
柚原 俊一
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ジャーナル フリー

23 巻 (1981) 5 号 p. 324-337

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In recent years, considerable progress has been made and experience has been obtained for material applicability in sodium-cooled fast breeder reactors.
In this report, materials, principal dimensions and sodium conditions for the reactor system components, which include fuel pin cladding, intermediate heat exchangers, steam generators and pipings, are reviewed with emphasis on the thin-walled, high temperature and high strength components. The corrosion, mechanical and tribological behavior in sodium of important materials used for the reactor components, such as Types 304 and 316 stainless steel and 21/4Cr-1Mo steel, are discussed on the basis of characteristic testing results. Furthermore, material requirements concerned with compatibility in sodium are summarized from this review and discussion.

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© by the Atomic Energy Society of Japan
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