Safety Evaluation for Crack-Grown of Nuclear Power Reactor Components
碩士 === 國立臺灣大學 === 機械工程學研究所 === 92 === 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 pe...
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| Format: | Others |
| Language: | zh-TW |
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2004
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| Online Access: | http://ndltd.ncl.edu.tw/handle/16161470835138776810 |
| Summary: | 碩士 === 國立臺灣大學 === 機械工程學研究所 === 92 === 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.
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