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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.9
- 수록면
- 3,112 - 3,121 (10page)
- DOI
- https://doi.org/10.1016/j.net.2021.03.029
이용수
초록· 키워드
오류제보하기
One of the major factors affecting the life span of a Reactor Pressure Vessel (RPV) is the PressurisedThermal Shock (PTS). PTS is a thermo-mechanical load on the RPV wall due to steep temperature gradientsand structural load created by internal pressure of the fluid within the RPV. Safe operating life of anuclear power plant is ensured by carrying out fracture analysis of the RPV against thermal shock.
Carrying out fracture tests on RPV/large scale components is not always feasible. Hence, studies onlaboratory level specimens are necessary to validate and supplement the prototype results. This paperaims to study the fracture behaviour of standard Compact Tension [C(T)] specimens, made of RPV steel20MnMoNi55, subjected to thermal shock through experimental and numerical investigations. Fracturetests have been carried out on the C(T) specimens subjected to thermal transient load and tensile load toquantify the effect of thermal shock. Crack resistance curves are obtained from the fracture tests as perASTM E1820 and compared with those obtained numerically using XFEM and a good agreement wasfound. A quantitative study on the crack tip plastic zone, computed using cohesive segment approach,from the numerical analyses justified the experimental crack initiation toughness.
목차
등록된 정보가 없습니다.
참고문헌 (2)
참고문헌 신청
남현석 / 2016 / Numerical Ductile Tearing Simulation of Circumferential Cracked Pipe Tests under Dynamic Loading Conditions / Nuclear Engineering and Technology 48(5):1252~1263
Li Xiangqing / 2020 / Effects of temperature on the local fracture toughness behavior of Chinese SA508-III welded joint / Nuclear Engineering and Technology 52(8):1732~1741
Li Xiangqing / 2020 / Effects of temperature on the local fracture toughness behavior of Chinese SA508-III welded joint / Nuclear Engineering and Technology 52(8):1732~1741
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