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Volume 42 Issue S2
Dec.  2021
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Huang Tao, Li Zhongchun, Sun Wei, Deng Jian, Ding Shuhua, Liu Yu, Wu Dan, Qian Libo, Shen Yaou, Du peng, Wu Zenghui. Application of DMRM on LOCA Integrated Effect Experiment[J]. Nuclear Power Engineering, 2021, 42(S2): 109-112. doi: 10.13832/j.jnpe.2021.S2.0109
Citation: Huang Tao, Li Zhongchun, Sun Wei, Deng Jian, Ding Shuhua, Liu Yu, Wu Dan, Qian Libo, Shen Yaou, Du peng, Wu Zenghui. Application of DMRM on LOCA Integrated Effect Experiment[J]. Nuclear Power Engineering, 2021, 42(S2): 109-112. doi: 10.13832/j.jnpe.2021.S2.0109

Application of DMRM on LOCA Integrated Effect Experiment

doi: 10.13832/j.jnpe.2021.S2.0109
  • Received Date: 2021-07-19
  • Accepted Date: 2021-12-07
  • Rev Recd Date: 2021-11-17
  • Publish Date: 2021-12-29
  • China Nuclear Power Research and Design Institute independently developed the loss of coolant accident (LOCA) evaluation model of Deterministic Model-Realistic Method (DMRM), and developed the advanced reactor system analysis code ARSAC based on the model. In this paper, this method is applied to large-break LOCA conditions to verify the correctness and rationality of the method. In the verification process, firstly, a conservative bench system model is established through sensitivity analysis; On this basis, the input conditions (system pressure, safety injection tank water temperature, etc.) that have a great impact on the peak cladding temperature (PCT) are randomly sampled to form 59 groups of working conditions for calculation and analysis; These working conditions are analyzed by ARSAC to obtain the final results, and the final results are compared with the experimental data. The results show that the pressure and other parameters calculated by the code are consistent with the experimental data, which proves the correctness of the ARSAC calculation; the PCT temperature obtained by DMRM is significantly higher than the experimental value, which proves the conservativeness of DMRM.

     

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