SUS316ステンレス鋼の照射材-未照射材溶接における健全性評価

Integrity evaluation for welding of irradiated and un-irradiated type 316 stainless steels

柴田 晃 ; 中村 夏紀 ; 二川 正敏  ; 前川 克廣*

Shibata, Akira; Nakamura, Natsuki; Futakawa, Masatoshi; Maekawa, Katsuhiro*

日本原子力研究開発機構は照射誘起応力腐食割れ(IASCC)研究の一環として、材料試験炉内におけるステンレス鋼のき裂進展試験の実施を計画している。当該試験ではIASCCのしきい値(610n/m (1MeV))以上に予備照射が行われたSUS316鋼と未照射のSUS316鋼の溶接が必要となる。照射材-未照射材の溶接健全性を確認するために、原子炉内で照射下材料から試験片を作り、照射材-未照射材の溶接試験を実施し、その健全性評価を行った。

Welding between irradiated and un-irradiated type 316 stainless steel is demanded for in-pile IASCC tests in Japan Materials Testing Reactor. Specimens were made from type 316 stainless steel which was irradiated up to 610 n/m( 1 MeV) in Reactor and welding tests of irradiated and un-irradiated type 316 stainless steels were performed to confirm integrity of the welding. Relationship between heat input and amount of Helium bubbles in welding bead was evaluated and hardness test was performed. It appeared that there is threshold value of heat input for welding without problem.