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。
Background: Reactor vessel auxiliary cooling system(RVACS) is a passive residual heat removal system applied to thorium molten salt reactor-solid fuel(TMSR-SF1). There are difficulties to use it to high-power reactor with its multifunction reactor vessel. To maximize vessel integrity, vessel should be minimized. Purpose: This study aims to verify the heat-discharge capability of the RVACS under station blackout accident(SBO). Methods: With a 10-MW fluoride salt-cooled high-temperature reactor(FHR) designed by Shanghai Institute of Applied Physics of Chinese Academy of Sciences as the baseline design, the RELAP5-MS code was adopted to simulate the transients during a SBO. Results: A scope of RVACS power for heat dissipation of FHR under SBO is given by this study. Conclusion: The heat-discharge capability of the RVACS was verified.
作者
赵晶
王凯
焦小伟
何兆忠
陈堃
ZHAO Jing WANG Kai JIAO Xiaowei HE Zhaozhong CHEN Kun(Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Jiading Campus, Shanghai 201800, China University of Chinese Academy of Sciences, Beijing 100049, China)
出处
《核技术》
CAS
CSCD
北大核心
2017年第9期77-83,共7页
Nuclear Techniques
基金
中国科学院战略性先导科技专项(No.XDA02050100)资助~~