Effects of temperature on the local fracture toughness behavior of Chinese SA508-III welded joint

Li Xiangqing; Ding Zhenyu; Liu Chang; Bao Shiyi; Qian Hao; Xie Yongcheng; Gao Zengliang

doi:10.1016/j.net.2020.01.020

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자료유형: 학술저널

저자정보: Li Xiangqing (Institute of Process Equipment and Control Engineering, Zhejiang University of Technology) Ding Zhenyu (Institute of Process Equipment and Control Engineering Zhejiang University of Technology) Liu Chang (Shanghai Nuclear Engineering Research and Design Institute Shangha) Bao Shiyi (a Institute of Process Equipment and Control Engineering Zhejiang University of Technology) Qian Hao (Shanghai Nuclear Engineering Research and Design Institute,) Xie Yongcheng (Shanghai Nuclear Engineering Research and Design Institute,) Gao Zengliang (Institute of Process Equipment and Control Engineering, Zhejiang University of Technology)

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제52권 제8호

발행연도: 2020.8

수록면: 1,732 - 1,741 (10page)

DOI: 10.1016/j.net.2020.01.020

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The structural integrity of welded joints in the reactor pressure vessel (RPV) is directly related to the safety of nuclear power plants. The RPV is made from SA508-III steel in a pressurized water reactor. In this study, we investigated the effects of temperature on the tensile and fracture toughness properties of Chinese SA508-III welded joint in different sampling areas in order to provide reference data for structural integrity assessments of RPVs. The specimens used in tensile and fracture toughness tests were fabricated from the base metal (BM), weld metal (WM), and the heat-affected zone (HAZ) in the welded joint. The representative testing temperatures included the ambient temperature (20 C), upper shelf temperature (100 C), and service temperature (320 C). The results showed that temperature greatly affected the fracture toughness (JIC) values for the SA508-III welded joint. The JIC values for BM and HAZ both decreased remarkably from 20 C to 320 C. The fracture morphologies showed that the BM and HAZ in the welded joint exhibited fully ductile fracture at 20 C, whereas partial cleavage fracture was mixed in ductile fracture mode at 100 C and 320 C. The WM exhibited the ductile and cleavage fracture mixed mode at various temperatures, and the JIC values showed slight changes

#Elevated temperature #Fracture toughness #Reactor pressure vessel steel #Unified J-integral resistance curve #Welded joint

참고문헌 (32)

참고문헌 신청

N. Irvine / 2017 / Nuclear Welding: Potential and Challenges for Lasers, 50Years of Laser Cutting :20

J. Xing / 2016 / HPR 1000 : advanced pressurized water reactor with active and passive safety / Eng. Times 2:79~87

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A. F. Mark / 2012 / On the evolution of local material properties and residual stress in a three-pass SA508 steel weld / Acta Mater 60:3268~3278

S. Kumar / 2017 / Experimental investigation of local tensile and fracture resistance behaviour of dissimilar metal weld joint : SA508Gr. 3 Cl. 1 and SA312 Type 304LN / Fatig. Fract. Eng. Mater. Struct 40:190~206

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