INTEGRITY ANALYSIS OF MAIN PUMP SHAFT SEAL UNDER ACCIDENTS INDUCED BY SBO FOR CANDU

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  • You Ximing
    Wuhan Second Ship Design and Research Institute
  • Wang Qianglong
    Wuhan Second Ship Design and Research Institute
  • Qiu Jinrong
    Wuhan Second Ship Design and Research Institute School of Nuclear Science and Technology, Xi’an Jiao Tong University
  • Yao Shiwei
    Wuhan Second Ship Design and Research Institute
  • Tong Lili
    School of Mechanical Engineering, Shanghai Jiao Tong University

抄録

The main pump shaft seal of Primary Heat Transport System (PHTS) is of great significance for the integrity of reactor coolant pressure boundary in CANada Deuterium Uranium (CANDU) nuclear power plant. The analysis model of CANDU nuclear power plant in China is built by RELAP5 code, including primary heat transport system, secondary system and moderator system. The applicability of the CANDU nuclear power plant analysis model is verified based on steady-state debugging and Design Basis Accident (DBA) analysis. The different accident scenarios induced by Station BlackOut (SBO) accident are analysis. The temperature and pressure change of main pump are studied based on the analysis model. Combined with relevant evaluation criteria, the integrity of main pump shaft seal is assessed.

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