Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Study on the influence of flow blockage in severe accident scenario of CAP1400 reactor

  • Pengcheng Gao (School of Nuclear Science and Technology, Xi'an Jiaotong University) ;
  • Bin Zhang (School of Nuclear Science and Technology, Xi'an Jiaotong University) ;
  • Jishen Li (School of Nuclear Science and Technology, Xi'an Jiaotong University) ;
  • Fan Miao (School of Nuclear Science and Technology, Xi'an Jiaotong University) ;
  • Shaowei Tang (School of Nuclear Science and Technology, Xi'an Jiaotong University) ;
  • Sheng Cao (School of Nuclear Science and Technology, Xi'an Jiaotong University) ;
  • Hao Yang (School of Nuclear Science and Technology, Xi'an Jiaotong University) ;
  • Jianqiang Shan (School of Nuclear Science and Technology, Xi'an Jiaotong University)
  • Received : 2022.07.16
  • Accepted : 2022.11.26
  • Published : 2023.03.25
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Abstract

Deformed fuel rods can cause a partial blockage of the flow area in a subchannel. Such flow blockage will influence the core coolant flow and further the core heat transfer during the reflooding phase and subsequent severe accidents. Nevertheless, most of the system analysis codes simulate the accident process based on the assumed flow blockage ratio, resulting in inconsistencies between simulated results and actual conditions. This paper aims to study the influence of flow blockage in severe accident scenario of the CAP1400 reactor. First, the flow blockage model of ISAA code is improved based on the FRTMB module. Then, the ISAA-FRTMB coupling system is adopted to model and calculate the QUENCH-LOCA-0 experiment. The correctness and validity of the flow blockage model are verified by comparing the peak cladding temperature. Finally, the DVI Line-SBLOCA accident is induced to analyze the influence of flow blockage on subsequent CAP1400 reactor core heat transfer and core degradation. From the results of the DVI Line-SBLOCA accident analysis, it can be concluded that the blockage ratio is in the range of 40%-60%, and the position of severe blockage is the same as that of cladding rupture. The blockage reduces the circulation area of the core coolant, which in turn impacts the heat exchange between the core and the coolant, leading to the early failure and collapse of some core assemblies and accelerating the core degradation process.

Keywords

References

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