Safety Evaluation for Crack-Grown of Nuclear Power Reactor Components
Date Issued
2004
Date
2004
Author(s)
Bao, Hung-Tsung
DOI
zh-TW
Abstract
The three nuclear power plants in Taiwan have been in operation for many years. Besides the impending requirements, all power plants are alike, after years of service, components inevitably cracked under repeated stress and corrosion.
This project is aimed at performing safety evaluation for some cracked components of the boiling water reactor (BWR) and pressurized water reactor (PWR). After choosing component, we would consider the possible loading combinations. Finite element analysis will be used to combine with fracture mechanics and limit load analysis method. Critical crack length and residual life of the component under loading will be determined from these analyses.
Subjects
有限元素分析
極限負載
沸水式
破壞力學
壓水式
Limit load analysis
Boiling water reactor
Pressurized water reactor
Fracture mechanics
Finite element analysis
Type
thesis
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