FHR在全厂断电事故下对RVACS散热能力的要求

发布时间：2018-05-28 01:34

本文选题：氟盐冷却高温堆 + 反应堆容器辅助冷却系统　；参考：《核技术》2017年09期

【摘要】：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。
[Abstract]:Fluorine salt cooled high temperature reactor (Fluoride salt-cooled High-temperature ReactorFHR) is an advanced reactor with coated granular fuel and high temperature melt fluorine salt coolant. Some of the FHR concepts are derived from reactor Vessel Auxiliary Cooling system RVACSs by passive processes such as heat conduction, convection heat transfer, radiation heat transfer and so on. The residual heat of reactor core is discharged into the atmosphere at the time of the accident. In this paper, the transient process of 10 MW FHR designed by Shanghai Institute of Applied Physics of Chinese Academy of Sciences is simulated by using RELAP5-MS program, and the residual heat transfer ability of RVACS is verified. In this paper, the transient process of power failure of the whole plant under the condition of high reactor power is further studied, and the requirements of FHR with different reactor power on the heat dissipation capacity of RVACS are discussed.
【作者单位】：中国科学院上海应用物理研究所嘉定园区;中国科学院大学;
【基金】：中国科学院战略性先导科技专项(No.XDA02050100)资助~~
【分类号】：TL364.4

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