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Influence of microstructure on IASCC growth behavior of neutron irradiated type 304 austenitic stainless steels in simulated BWR condition

BWR模擬環境における304ステンレス鋼照射材のIASCC進展挙動に及ぼすミクロ組織の影響

加治 芳行 ; 三輪 幸夫*; 柴田 晃 ; 中野 純一; 塚田 隆 ; 高倉 賢一*; 仲田 清智*

Kaji, Yoshiyuki; Miwa, Yukio*; Shibata, Akira; Nakano, Junichi; Tsukada, Takashi; Takakura, Kenichi*; Nakata, Kiyotomo*

JMTRにおいて288$$^{circ}$$C、BWR模擬水質で照射したコンパクトテンション(CT)試験片を用いてき裂進展試験を実施した。腐食電位が高い条件で応力拡大係数が10から30MPam$$^{1/2}$$の範囲では、2dpaまでは中性子照射量が増加するにしたがって、き裂進展速度が増加するが、2から10dpaの範囲ではほぼ同じ値となる。ミクロ組織観察や析出物周辺の局所ひずみ測定などにより、き裂進展速度に及ぼすミクロ組織の影響を調べた。本論文では、き裂進展速度とミクロ組織,照射硬化,照射誘起偏析の関係について議論した。

Crack growth rate (CGR) tests have been conducted with neutron irradiated compact tension (CT) specimens. The specimens were irradiated in the core region of the Japan Materials Testing Reactor (JMTR) in simulated BWR water environments at 288 $$^{circ}$$C from 0.37 to 5.55$$times$$10$$^{25}$$ n/m$$^{2}$$ (E$$>$$ 1 MeV) (0.62 to 9.2 dpa). The CGRs of base metals in high electrochemical corrosion potential (ECP) condition with 10 $$<$$ stress intensity factor, K $$<$$ 30 MPam$$^{1/2}$$, increased with increasing neutron fluence until 2 dpa and the CGRs were almost the same from 2 to 10 dpa. We investigated the influence of microstructure on CGR by microstructure observation and local strain measurement around the precipitate. This paper will discuss the relationship between CGR and microstructure, radiation hardening, radiation induced segregation.

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