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Causes and Remedies for the Degradation of Steam Generator Tubings in Korean Nuclear Power Plants
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관련 논문AI추천
증기발생기 전열관 감육부의 강도 및 손상평가남기우, 성기용, 안석환, 윤자문한국해양공학회 · 한국해양공학회지2007 · 제21권 제2호Study on Leak Rate of SCC Degraded Alloy 600 Tubings of PWRs김정수, 황성식, Jang Yul Park, Ken E. Kasza한국재료부식학회 · CORROSION SCIENCE AND TECHNOLOGY2004 · 제3권 제6호누설 및 파열실험용 SCC 결함 전열관 제작 및 누설거동 평가김홍표, 정만교, 황성식한국재료부식학회 · CORROSION SCIENCE AND TECHNOLOGY2009 · 제8권 제5호Factors Affecting Stress Corrosion Cracking Susceptibility of Alloy 600 MA Steam Generator Tubes강용석, 신동만, 이국희한국재료부식학회 · CORROSION SCIENCE AND TECHNOLOGY2021 · 제20권 제1호A Study on the Evaluation Technology of Welds Integrity inNuclear Power PlantsHyun-Young Chang, Jong-Sung Kim, Tae-Eun Jin한국재료부식학회 · CORROSION SCIENCE AND TECHNOLOGY2007 · 제6권 제1호Relationship Between the Initiation and Propagation of SCC and the Electrochemical Noise of Alloy 600 for the Steam Generator Tubing of Nuclear Power Plants권용혁, 김영식, 남희수, 장현영, H.P.Kim, S.W.Kim한국재료부식학회 · CORROSION SCIENCE AND TECHNOLOGY2010 · 제9권 제2호
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