Transactions of the Korean Society of Pressure Vessels and Piping (한국압력기기공학회 논문집)
- Volume 8 Issue 1
- /
- Pages.8-18
- /
- 2012
- /
- 1738-8333(pISSN)
DOI QR Code
Effect of Finite Element Analysis Parameters on Weld Residual Stress of Dissimilar Metal Weld in Nuclear Reactor Piping Nozzles
유한요소 해석변수가 원자로 배관 노즐 이종금속용접부의 용접잔류응력에 미치는 영향
- Soh, Na-Hyun ;
- Oh, Gyeong-Jin ;
-
Huh, Nam-Su
;
- Lee, Sung-Ho ;
-
Park, Heung-Bae
(KEPCO) ;
- Lee, Seung-Gun (KEPCO) ;
-
Kim, Jong-Sung
;
-
Kim, Yun-Jae
- 소나현 (서울과학기술대학교 기계시스템디자인공학과) ;
- 오경진 (서울과학기술대학교 기계시스템디자인공학과) ;
-
허남수
(서울과학기술대학교 기계시스템디자인공학과) ;
- 이성호 (한국수력원자력(주) 중앙연구원) ;
-
박흥배
;
- 이승건 ;
-
김종성
(순천대학교 기계공학과) ;
-
김윤재
(고려대학교 기계공학과)
- Received : 2011.11.17
- Accepted : 2012.01.31
- Published : 2012.03.01
Abstract
In early constructed nuclear power plants, Ni-based Alloys 82/182 had been widely used for dissimilar metal welds (DMW) as a weld filler metal. However, Alloys 82/182 have been proven to be susceptible to primary water stress corrosion cracking (PWSCC) in the nuclear primary water environment. The formation of crack due to PWSCC is also influenced by weld residual stresses. Thus, the accurate estimation of weld residual stresses of DMW is crucial to investigate the possibility of PWSCC and instability behaviors of crack due to PWSCC. In this context, the present paper investigates weld residual stresses of nuclear reactor piping nozzles based on 2-D axi-symmetric finite element analyses based on layer-based approach using maximum molten bead temperature. In particular, the effect of analysis parameters, i.e., a thickness of weld layer, an initial molten bead temperature, convection heat transfer coefficient, and geometric constraints on predicted weld residual stresses was investigated.
Keywords
- Weld Residual Stress;
- Dissimilar Metal Weld;
- Primary Water Stress Corrosion Cracking;
- Finite Element Analysis
- 용접잔류응력;
- 이종금속용접;
- 일차수 응력부식균열;
- 유한요소해석;