Nuclear Engineering and Technology

  • 제55권8호
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  • Pages.2835-2843
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  • 2023
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Development of reduced-order thermal stratification model for upper plenum of a lead-bismuth fast reactor based on CFD

  • Tao Yang (School of Nuclear Science and Technology, University of South China) ;
  • Pengcheng Zhao (School of Nuclear Science and Technology, University of South China) ;
  • Yanan Zhao (School of Nuclear Science and Technology, University of South China) ;
  • Tao Yu (School of Nuclear Science and Technology, University of South China)
  • 투고 : 2022.10.20
  • 심사 : 2023.05.01
  • 발행 : 2023.08.25
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초록

After an emergency shutdown of a lead-bismuth fast reactor, thermal stratification occurs in the upper Plenum, which negatively impacts the integrity of the reactor structure and the residual heat removal capacity of natural circulation flow. The research on thermal stratification of reactors has mainly been conducted using an experimental method, a system program, and computational fluid dynamics (CFD). However, the equipment required for the experimental method is expensive, accuracy of the system program is unpredictable, and resources and time required for the CFD approach are extensive. To overcome the defects of thermal stratification analysis, a high-precision full-order thermal stratification model based on CFD technology is prepared in this study. Furthermore, a reduced-order model has been developed by combining proper orthogonal decomposition (POD) with Galerkin projection. A comparative analysis of thermal stratification with the proposed full-order model reveals that the reduced-order thermal stratification model can well simulate the temperature distribution in the upper plenum and rapidly elucidate the thermal stratification interface characteristics during the lead-bismuth fast reactor accident. Overall, this study provides an analytical tool for determining the thermal stratification mechanism and reducing thermal stratification.

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과제정보

This work is supported by the "Coupled Response Mechanism of Lead-based Fast Reactor Hot Pool and Cold Pool Thermal stratification under Asymmetric Thermal Load Condition and its Influence on Natural Circulation Performance" project sponsored by National Natural Science Foundation of China (Grant No. 11905101).

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