摘要
为满足压水堆大破口LOCA分析的需要,在移植和开发TRAC-PF1程序中,应用了一种新颖的进行再淹没骤冷前沿处燃料元件温度场分析的方法。本文对这种方法及与之相关的燃料元件热传导数值模型、锆水反应和气隙传热计算进行了简要的描述。
In order to meet the need of large break LOCA analysis of PWR, an innovative method was employed by TRAC-PF1, a code transplanted and developed by us, to process the analysis of temperature field of fuel element in the vicinity of quench-front during reflood phase. This paper gives a concise description of the method and numerical heat conduction model of fuel element, metal-water reaction and evaluation of fuel-clad gap heat transfer coefficient related to the method.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
1991年第5期39-44,共6页
Nuclear Power Engineering