Nemoto, Yoshiyuki 
; Miwa, Yukio; Tsuji, Hirokazu; Tsukada, Takashi
Irradiation assisted stress corrosion cracking (IASCC) of austenitic stainless steel has been studied as main concern of an aging problem of light water reactor (LWR) materials. It is essential to evaluate corrosion behavior of irradiated materials for mechanistic understanding of IASCC. The aim of this work is to evaluate the corrosion behavior of ion irradiated materials using atomic force microscope (AFM), and evaluate the influence of radiation temperature, radiation damage, H and He implantation.
Language |
: | English |
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Journal |
: | Proceedings of 11th International Conference on Nuclear Engineering (ICONE-11) (CD-ROM) |
Volume |
: | |
Number |
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Pages |
: | 7 Pages |
Publication Year/Month |
: | 2003/04 |
Meeting title |
: | 11th International Conference on Nuclear Engineering (ICONE-11) |
Held date |
: | 2003/04 |
Location (city) |
: | Tokyo |
Location (country) |
: | Japan |
Paper URL |
: |
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Keywords |
: | IASCC; AFM; Ion Irradiation; Corrosion Behavior; Implantation; TIARA; LWR |
Research Facility |
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