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原子炉圧力容器用鋼Ａ５３３Ｂの高温高圧水中疲労き裂伝ぱ挙動
(Fatigue Crack Growth Behavior of Reactr Pressure Vessel Steel A533B Cl.1 in High Temperature Pressurized Water)
日本鉄鋼協会. 1982-09-28.
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Fulltext and dataset(s) on Materials Data Repository (MDR)
Created at: 2017-02-18 00:04:38 +0900 Updated at: 2017-07-10 17:01:08 +0900