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Development of a RVIES Syetem for Reactor Vessel Integrity Evaluation
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 Title & Authors
Development of a RVIES Syetem for Reactor Vessel Integrity Evaluation
Lee, Taek-Jin; Choe, Jae-Bung; Kim, Yeong-Jin; Park, Yun-Won; Jeong, Myeong-Jo;
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In order to manage nuclear power plants safely and cost effectively, it is necessary to develop integrity evaluation methodologies for the main components. Recently, the integrity evaluation techniques were broadly studied regarding the license renewal of nuclear power plants which were approaching their design lives. Since the integrity evaluation process requires special knowledges and complicated calculation procedures, it has been allowed only to experts in the specified area. In this paper, an integrity evaluation system for reactor pressure vessel was developed. RVIES(Reactor Vessel Integrity Evaluation System) provides four specific integrity evaluation procedures covering PTS(Pressurized Thermal Shock) analysis, P-T(Pressure-Temperature) limit curve generation, USE(Upper Shelf Energy) analysis and Fatigue analysis. Each module was verified by comparing with published results.
ASME Sec. Xl;Reactor Pressure Vessel;Stress Intensity Factor;PTS;P-T Limit Curve;USE;Fatigue Analysis;
 Cited by
유한요소해석을 이용한 원자로용기 압력-온도 한계곡선의 평가,이택진;박윤원;이진호;최재붕;김영진;

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