压水堆燃料棒芯块事故后传热的简化分析  

Simplified Method on the Heat Conduction of PWR Fuel Rods During the Accident

作　　者：齐宇博 张伟 于江 南金秋 赵剑刚 QI Yubo;ZHANG Wei;YU Jiang;NAN Jinqiu;ZHAO Jiangang(China Nuclear Power Technology Research Institute Co.,Ltd,Shenzhen of Guangdong Prov.518124,China)

机构地区：[1]中广核研研究院有限公司,广东深圳518124

出　　处：《核科学与工程》2022年第1期53-58,共6页Nuclear Science and Engineering

基　　金：国家科技支撑计划(2011BAA06B01)资助。

摘　　要：压水堆核电厂在严重事故下,堆芯换热条件恶劣,此时包含衰变热的堆芯非稳态传热分析过程较为复杂。本文以大亚湾核电厂M310机组一回路热段双端断裂为假想工况,用简化分析方法研究事故后衰变热的传递情况,获得了含时间变量的温度场简化计算公式。采用ANSYS有限元分析软件,用非简化分析的方法计算分析,两种方法对比验证。研究结果显示:在一定条件下,简化计算的误差相对较小,可采取简化分析方法对事故后燃料棒芯块的传热进行计算。本文的简化方法不仅局限于压水堆,其他堆型的事故分析亦可借鉴。During the serious accident of PWR nuclear power plants,such as a loss of coolant accident,the analysis of core decay heat transfer will be complicated。This paper is based on the hypothetical condition of a double-ended loop break of the Daya Bay M310 and uses simplified method to research the decay heat transfer,by which getting the simplified calculating formula of the temperature filed via the time variable.Meanwhile,the results of the calculation are compared with the results of ANSYS software to testify.The results have showed that the errors of calculations can be accepted when taking a simplified analytical method on a certain conditions.This simplified analytical method not only can be used for PWR,but is also available for the other types of reactors.

关 键 词：瞬态导热 集总参数法 有限元法 严重事故 

分 类 号：TLLT331[核科学技术]