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氟盐冷却高温堆(Fluoride salt-cooled High-temperature Reactor,FHR)是一种采用包覆颗粒燃料、高温熔融氟盐冷却剂的先进反应堆。部分FHR概念采用了反应堆容器辅助冷却系统(Reactor Vessel Auxiliary Cooling System,RVACS)导出事故下的堆芯余热。RVACS通过导热、对流换热、辐射换热等非能动过程,在事故发生时将堆芯余热排出至大气中。本文采用中国科学院上海应用物理研究所设计的10 MW FHR作为基准,利用RELAP5-MS程序,对其在全厂断电事故下的瞬态过程进行了模拟,验证了RVACS的余热导出能力。本文进一步研究了高反应堆功率情况下的全厂断电事故的瞬态过程,探讨了不同反应堆功率的FHR对RVACS散热能力的要求。
Fluoride salt-cooled High-temperature Reactor (FHR) is an advanced reactor that uses a coated pellet fuel and a high-temperature molten fluoride salt coolant. Some FHR concepts use Reactor Vessel Auxiliary Cooling System (RVACS) to derive core residual heat from accidents. RVACS discharges the residual heat of the core to the atmosphere through heat transfer, convective heat transfer, radiation heat exchange and other non-active processes. In this paper, the 10 MW FHR designed by the Shanghai Institute of Applied Physics, Chinese Academy of Sciences was used as a benchmark. The transient process under power failure of the whole plant was simulated by RELAP5-MS program, and the residual heat derivation ability of RVACS was verified. In this paper, the transient process of power plant blackout under high reactor power is further studied, and the requirements of FACS on the cooling capacity of RVACS are discussed.