核动力装置小破口失水事故的瞬态性模拟与处置研究

Transient Property Simulating and Dealing of Small-Break Loss-of-Coolant Accident in Nuclear Power Plant

以非均匀不平衡态两相流模型为基础，采用快速的半隐式有限差分的数值方法进行求解，研制了核动力装置运行分析程序，并应用该程序分析了核动力装置小破口失水事故的瞬态特性，提出了事故处置方法。

Nuclear power plant operation analysis code is designed and developed. Based on nonhomogeneous and nonequilibrium model for the two-phase flow it is a fast partially implicit numerical scheme. The is program used to analyze transient property of a small-break loss-of-coolant accident in nuclear power unit. The method to deal the accident are proposed.