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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.1
- 수록면
- 22 - 25 (4page)
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초록· 키워드
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In the past, Alloy 600 nickel-based alloys have been widely used in steam generators. However, most of them have been replaced by thermally treated alloy 690 tubes in recent years because mill annealed alloy 600 materials are known to be susceptible to stress corrosion cracking. Unlike this general perception, somesteam generators using mill annealed alloy 600 tubes show excellent performance even though they are designed, manufactured, and operated in the same way. Therefore, various analyses were carried out to determine causes for the degradation of steam generators. Based on the general stress corrosion crackingmechanism, tube material susceptibility, residual stress, and sludge deposits of steam generators were compared to identify factors affecting stress corrosion cracking. It was found that mill annealed alloy 600 steam generator tubes showed higher resistance to stress corrosion cracking when the amount of sludge deposits on tube surface was smaller and residual stress generated during the fabrication was lower.
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참고문헌 (6)
참고문헌 신청
H. Cothron / 2016 / Generator Management Program:Steam Generator Integrity Assessment Guidelines:Revision 4 / EPRI :6~5
EPRI SGDD Website
2011 / Assessment and Management of Aging of Major Nuclear Power Plant Components Important to Safety: Steam Generators / IAEA-TECDOC-1668 :29~30
I. Peter / 1994 / Steam Generator Reference Book Revision 1:4~5
2014 / Detection of ODSCC in SG tubes depending on the size of the crack and on the presence of sludge deposits, Aug. 2014 / Nuclear Engineering and Technology 46(6)
EPRI SGDD Website
2011 / Assessment and Management of Aging of Major Nuclear Power Plant Components Important to Safety: Steam Generators / IAEA-TECDOC-1668 :29~30
I. Peter / 1994 / Steam Generator Reference Book Revision 1:4~5
2014 / Detection of ODSCC in SG tubes depending on the size of the crack and on the presence of sludge deposits, Aug. 2014 / Nuclear Engineering and Technology 46(6)
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