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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2019.1
- 수록면
- 479 - 489 (11page)
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초록· 키워드
오류제보하기
Low-cycle fatigue (LCF) tests were performed for Alloy 690 and 316 SS in a simulated pressurized waterreactor (PWR) environment. Alloy 690 showed about twice longer LCF life than 316 SS at the test conditionof 0.4% amplitude at strain rate of 0.004%/s. Observation of the oxide layers formed on the fatiguecrack surface showed that Cr and Ni rich oxide was formed for Alloy 690, while Fe and Cr rich oxide for316 SS as an inner layer. Electrochemical analysis revealed that the oxide layers formed on the LCF cracksurface of Alloy 690 had higher impedance and less defect density than those of 316 SS, which resulted inlonger LCF life of Alloy 690 than 316 SS in a simulated PWR environment
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참고문헌 (36)
참고문헌 신청
T. Couvant / 2013 / Materials’ Ageing and Degradation in Light Water Reactors / Woodhead Publishing :70~80
T. Allen / 2010 / Materials challenges for nuclear systems / Mater. Today 13:14~23
M. Higuchi / 2007 / Codes Stand, vol. 1 / ASME :111~122
O. Chopra / 2014 / Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials
장창희 / 2013 / Environmental Fatigue of Metallic Materials in Nuclear Power Plants – A Review of Korean Test Programs / Nuclear Engineering and Technology 45(7):929~940
T. Allen / 2010 / Materials challenges for nuclear systems / Mater. Today 13:14~23
M. Higuchi / 2007 / Codes Stand, vol. 1 / ASME :111~122
O. Chopra / 2014 / Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials
장창희 / 2013 / Environmental Fatigue of Metallic Materials in Nuclear Power Plants – A Review of Korean Test Programs / Nuclear Engineering and Technology 45(7):929~940
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