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http://dx.doi.org/10.3795/KSME-A.2002.26.11.2219

Deterministic Fracture Mechanics Analysis of Nuclear Reactor Pressure Vessel Under Rot Leg Leak Accident  

Lee, Sang-Min (성균관대학교 기계공학부)
Choi, Jae-Boong (성균관대학교 기계공학부)
Kim, Young-Jin (성균관대학교 기계공학부)
Park, Youn-Won (한국원자력안전기술원)
Jhung, Myung-Jo (한국원자력안전기술원)
Publication Information
Transactions of the Korean Society of Mechanical Engineers A / v.26, no.11, 2002 , pp. 2219-2227 More about this Journal
Abstract
In a nuclear power plant, reactor pressure vessel (RPV) is the primary pressure boundary component that must be protected against failure. The neutron irradiation on RPV in the beltline region, however, tends to cause localized damage accumulation, leading to crack initiation and propagation which raises RPV integrity issues. The objective of this paper is to estimate the integrity of RPV under hot leg leaking accident by applying the finite element analysis. In this paper, a parametric study was performed for various crack configurations based on 3-dimensional finite element models. The crack configuration, the crack orientation, the crack aspect ratio and the clad thickness were considered in the parametric study. The effect of these parameters on the maximum allowable nil-ductility transition reference temperature ($(RT_{NDT})$) was investigated on the basis of finite element analyses.
Keywords
PTS(Pressurized Thermal Shock); Stress Intensity Factor; Finite Element Analysis; Surface Crack; Subclad Crack;
Citations & Related Records
Times Cited By KSCI : 2  (Citation Analysis)
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