Considerations for in-service inspection on pressure vessel of 200MW nuclear heating reactor |
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Authors: | Huajian Chang Shuyan He Junjie Liu |
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Affiliation: | Institute of Nuclear Energy Technology, Tsinghua University, Beijing 100084, China |
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Abstract: | The 200MW nuclear heating reactor adopts an integrated arrangement for the primary circuit. It is designed to be operated at lower temperature and lower pressure as compared to large reactors. A steel containment serves a barricade for the reactor pressure vessel. The pressure vessel has some safety characteristics, such as low stress level, low induced integral neutron flux, and high toughness etc. Among them, the most important is its LBB behavior. Based on the safety analysis for the pressure, the requirements and procedures of in-service inspection are layed-out accordingly. |
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