IASCC growth behavior evaluation of neutron-irradiated SUS304 stainless steel under BWR simulated high temperature water condition

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

SCC growth tests have been carried out using type 304 stainless steel that had been pre-irradiated 0.62 to 9.2dpa under BWR simulated high temperature water condition at 288 $^{circ}$ C in the JMTR. This paper describes the investigated results of crack growth rate characteristics from the point of view of microstructure, radiation hardening and radiation induced segregation.

Language	:	Japanese
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Meeting title	:	日本原子力学会2009年春の年会
Held date	:	2009/03
Location (city)	:	東京
Location (country)	:	日本
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Keywords	:	no keyword
Research Facility	:	JMTR(材料試験炉)
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Article of JAEA R&D Review	:
Cooperating Institute	:	原子力安全基盤機構

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Registration No. : BB20083597
JAEA Abstracts No. :
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