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Volume 37 Issue 2
Feb.  2025
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Liu Liang, Zhou Tao, Chen Jie, Fang Xiaolu, Chen Juan, Wei Xiaoyan, Xia Bangyang. Typical Accident Analysis of Supercritical Water-Cooled Reactor[J]. Nuclear Power Engineering, 2016, 37(2): 151-155. doi: 10.13832/j.jnpe.2016.02.0151
Citation: Liu Liang, Zhou Tao, Chen Jie, Fang Xiaolu, Chen Juan, Wei Xiaoyan, Xia Bangyang. Typical Accident Analysis of Supercritical Water-Cooled Reactor[J]. Nuclear Power Engineering, 2016, 37(2): 151-155. doi: 10.13832/j.jnpe.2016.02.0151

Typical Accident Analysis of Supercritical Water-Cooled Reactor

doi: 10.13832/j.jnpe.2016.02.0151
  • Received Date: 2015-10-11
  • Rev Recd Date: 2015-12-16
  • Available Online: 2025-02-15
  • CSR1000 was selected as the research object. A code named SCAC-CSR1000 has been developed based on the SCAC code. The reliability of the code was verified by comparing the results of SCAC-CSR1000 and SCTRAN. Then the safety analysis was carried out. Five events were selected, that are partial loss of reactor coolant flow, isolation of main steam line, uncontrolled CR withdrawal, reactor coolant pump seizure and loss of feed water heating. By the numerical analysis, it was found that the MCST does not exceed 1260℃, and meets the design safety requirements. The 2nd MCST are higher than the 1st MCST. The isolation of main steam line has the less safety margin.

     

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