Study on Optimization of Dissimilar friction Welding of Nuclear Power Plant Materials (Cu Alloy/STS316L) and Its Real Time AE Evaluation |
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원자력 발전소용 이종재(Cu 합금/STS316L) 마찰용접의 최적화와 AE에 의한 실시간 평가에 관한 연구 |
유인종,권상우,황성필,공유식,오세규 |
부경대학교 대학원,부경대학교 대학원,부경대학교 대학원,부경대학교 기계공학부,부경대학교 기계공학부 |
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© 2001 The Korean Society of Ocean Engineers
Open access / Under a Creative Commons License
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Keywords:
Friction welding (FRW), Acoustic emission(AE), Weld interface(W.I), Weld quality, Heat affected zone (HAZ), Tensile strength |
핵심용어:
마찰용접, 음향방출법, 용접계면, 용접품질, 열영향부, 인장강도 |
Abstract |
In this paper, joints of Cu-1Cr-0.1Zr alloy to STS316L were performed by friction welding method. Particularly, Cu-1Cr-0.1Zr alloy is attractive candidate as nuclear power plant material and exibit the best combination of high strength and good electrical and thermal conductivity of any copper alloy examined. The stainless steel is a structural material while copper alloy acts as a heat sink material for the surface heat flux in the first wall. So, in this paper, not only the development of optimizing of friction welding with more reliability and more applicability but also the development of in-process real-time weld quality (such as strength and toughness) evaluation technique by acoustic emission for friction welding of such nuclear reactor component of Cu-1Cr-0.1Zr alloy to STS316L steel sere performed. |
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