摘要
为了在事故条件下导出气冷微堆堆芯余热,本文提出了一种非能动余热排出系统(简称余排系统)设计。余排系统的自然循环流动换热和反应堆堆芯的温度分布具有紧密的耦合反馈作用,对于事故条件下的余排系统换热性能和燃料最高温度有重要影响。本文基于COMSOL Multiphysics软件,针对棱柱型气冷微堆设计,开发了包含反应堆堆芯和余排系统的一体化流动传热计算模型,并与MHTGR基准题和方腔自然对流基准题开展了关键模型验证。利用该计算模型分别研究了正常运行稳态和失流未失压事故瞬态工况下的余排系统工作特性以及堆芯温度响应状态,评估了该系统对事故的缓解效果。计算结果表明,正常运行工况下,余排系统空气自然循环流动规则平稳,带热造成的热损耗水平可以接受,不会显著影响堆芯温度。在失流未失压事故工况下,余排系统早期换热功率较高,后期由于压力容器壁面温度的下降而逐渐降低。总体而言,该系统能有效导出堆芯热量,从而保证堆芯结构的完整性。本文建立的一体化CFD计算模型能用于气冷微堆余排系统的方案设计以及事故安全分析评价。
A conceptual design of a passive core cooling system(PCCS)was proposed in order to removal residual core heat during accident scenarios.Strong coupling feedback effect exists between natural convective heat transfer of the PCCS and the temperature distribution within the reactor core,which has a significant impact on the heat removal performance of the PCCS and the peak fuel temperature.An integral computational model dedicated to micro gas-cooled reactor,which includes both the PCCS and the reactor core,was developed.Comparisons of results predicted by this model and reference results of two benchmark problem,i.e.exercises of MHTGR and natural convection in a square cavity,show a satisfactory agreement,which thus validate the model.Thereafter,in order to explore the operational characteristics of the PCCS proposed in this work as well as the temperature response of the reactor core,and to assess its mitigative performance during accident scenario,this CFD model was then employed to analyze both the steady state under normal operation condition and the pressurized-loss-of-forced-cooling(PLOFC)accident.The calculation results show that the natural circulation of air is steady and regular during normal operation.The heat loss due to the PCCS is acceptably small,which will not lead to significant impact on the core temperature.During the PLOFC accident,the heat removal power of the PCCS is high in the early phase,whereas its performance gradually decreases as the temperature of the reactor vessel decreases in the long term.In general,the PCCS can effectively remove the residual core heat,thus maintaining the reactor integrity.Consequently,the integral CFD model created in this work can be applied to the design and the safety analysis of the PCCS for the micro gas-cooled reactor.
作者
黄政
张朔婷
董建华
王贺南
刘国明
陈巧艳
堵树宏
HUANG Zheng;ZHANG Shuoting;DONG Jianhua;WANG Henan;LIU Guoming;CHEN Qiaoyan;DU Shuhong(Reactor Engineering Division,China Nuclear Power Engineering Co.,Ltd.,Beijing 100840,China)
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2023年第6期1182-1192,共11页
Atomic Energy Science and Technology
基金
中核集团“青年英才”项目。
