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https://www.riss.kr/link?id=O105418406
2017년
eng
학술저널
Proceedings of the international symposium on environmental degradation of materials in nuclear power systems water reactors
663-672 [※수록면이 p5 이하이면, Review, Columns, Editor's Note, Abstract 등일 경우가 있습니다.]
Environmental degradation of materials in nuclear power systems water reactors (International conference)
Portland, OR
Aug 2017
0
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Diffusion Processes as Possible Mechanisms for Cr Depletion at SCC Crack Tip
Oxidation and SCC Initiation Studies of Type 304L SS in PWR Primary Water
NRC Perspectives on Primary Water Stress Corrosion Cracking of High-Chromium, Nickel-Based Alloys