Behavior of stainless steels in pressurized water reactor primary circuits
作者： D. Féron , E. Herms , B. Tanguy
DOI: 10.1016/J.JNUCMAT.2012.03.034
关键词:
摘要: … Irradiation is involved in the stress corrosion cracking and corrosion of in-core reactor components in PWR environment. Irradiated assisted stress corrosion cracking (IASCC) is a …
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