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Relationship between crack growth rates and locally deformed structures in irradiated 316L stainless steels

照射316Lステンレス鋼におけるき裂進展速度と局所変形組織の関係

知見 康弘; 笠原 茂樹; 西山 裕孝; 瀬戸 仁史*; 橘内 裕寿*; 越石 正人*

Chimi, Yasuhiro; Kasahara, Shigeki; Nishiyama, Yutaka; Seto, Hitoshi*; Kitsunai, Yuji*; Koshiishi, Masato*

照射誘起応力腐食割れ(IASCC)進展挙動を理解するため、中性子照射した316Lステンレス鋼コンパクトテンション試験片を用いて、BWR模擬水質環境(約288$$^{circ}$$C)中でき裂進展試験を実施した。さらに、中性子照射した316Lステンレス鋼引張試験片にひずみを付加した後、変形組織について透過型電子顕微鏡(TEM)により観察した。その結果、低照射量領域($$<sim$$1.9dpa)では、き裂進展速度に環境緩和効果が見られ、変形組織は転位が絡み合ったものであった。一方、高照射量領域($$>sim$$2.7dpa)では、き裂進展速度の環境緩和効果が小さく、変形組織は主に転位チャンネルからなるものであった。き裂進展挙動と変形組織の関係から、IASCC進展機構に関して議論する。

In order to understand irradiation-assisted stress corrosion cracking (IASCC) growth behavior, crack growth tests using compact tension (CT) specimens made of neutron-irradiated 316L stainless steels (SSs) were performed in simulated BWR environments (at $$sim$$288$$^{circ}$$C). Moreover, microstructures of deformed areas were observed by transmission electron microscope (TEM) after straining tensile specimens made of neutron-irradiated 316L SSs. As a result, for lower neutron dose than $$<sim$$1.9 dpa, the crack growth rates (CGRs) show effective environmental mitigation and the deformed structures show tangling of dislocations. On the other hand, for higher neutron dose than $$>sim$$2.7 dpa, the CGRs show small environmental mitigation and the deformed structures consist mainly of dislocation channels. From the relationship between CGRs and deformed structures, mechanisms on IASCC growth will be discussed.

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