Takakura, Kenichi*; Tanaka, Shigeaki*; Nakamura, Tomomi*; Chatani, Kazuhiro*; Kaji, Yoshiyuki 
Irradiation Assisted Stress Corrosion Cracking (IASCC) is a matter of great concern as a degradation of core internal components in light water nuclear reactor. Japan Nuclear Energy Safety organization (JNES) had been conducting a project related to IASCC as a part of safety research and development study for the aging management and maintenance of the nuclear power plants. Based on the JNES project results, JNES proposed "IASCC evaluation guide for BWR core internals". The purpose of this paper is to describe the background of the guide, especially crack growth rate (CGR) tests for irradiated stainless steels.
Language |
: | English |
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Journal |
: | Proceedings of 2010 ASME Pressure Vessels and Piping Conference (PVP 2010) (CD-ROM) |
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Pages |
: | 10 Pages |
Publication Year/Month |
: | 2010/07 |
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Held date |
: | 2010/07 |
Location (city) |
: | Bellevue |
Location (country) |
: | U.S.A. |
Paper URL |
: |
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Keywords |
: | no keyword |
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