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Nowadays, there seems to be consensus that the shortage of energy resources is an essential issue to be solved, and investigating nuclear fusion reactors serves as one of the most important measures. However, the safety evaluation system of the blanket under accident conditions of the fusion reactor remains to be improved. Thus, this study applies the reactor thermal calculation program RELAP5 to analyze a sector of the water cooled solid blanket of China Fusion Engineering Test Reactor (CFETR). Based on the known blanket structure data and main operating parameters, we firstly calculated the operating parameters of steady-state CFETR and compared them with the actual design parameters. Then, transient calculations were conducted on two types of LOCA accidents including In-vessel LOCA (In-vessel Lost of Coolant Accident) and In-box LOCA (In-box Lost of Coolant Accident), to analyze the impacts on the thermal hydraulics parameters of CFETR. The results indicate that the pressure of the blanket and the temperature of first wall will not break the limit, and these two types of accidents in the water cooled solid blanket of CFETR will not produce adverse effects, allowing technicians to have sufficient time to remedy the accidents. In summary, this study can provide references for preventing the water cooled solid cladding rupture accident of CFETR.

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Analysis on the LOCA Accidents of Water Cooled Solid Breeder Blanket of the Fusion Reactor Under PWR Conditions

  • 会议论文

  • 发表日期：

    2026年

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  • Shuaiyu Han,
  • Chao Tian,
  • Futing Jing,
  • Jie Cheng

摘要

Nowadays, there seems to be consensus that the shortage of energy resources is an essential issue to be solved, and investigating nuclear fusion reactors serves as one of the most important measures. However, the safety evaluation system of the blanket under accident conditions of the fusion reactor remains to be improved. Thus, this study applies the reactor thermal calculation program RELAP5 to analyze a sector of the water cooled solid blanket of China Fusion Engineering Test Reactor (CFETR). Based on the known blanket structure data and main operating parameters, we firstly calculated the operating parameters of steady-state CFETR and compared them with the actual design parameters. Then, transient calculations were conducted on two types of LOCA accidents including In-vessel LOCA (In-vessel Lost of Coolant Accident) and In-box LOCA (In-box Lost of Coolant Accident), to analyze the impacts on the thermal hydraulics parameters of CFETR. The results indicate that the pressure of the blanket and the temperature of first wall will not break the limit, and these two types of accidents in the water cooled solid blanket of CFETR will not produce adverse effects, allowing technicians to have sufficient time to remedy the accidents. In summary, this study can provide references for preventing the water cooled solid cladding rupture accident of CFETR.