AP1000机组小破口失水事故模拟分析

华电技术 ›› 2016, Vol. 38 ›› Issue (1): 68-71.

AP1000机组小破口失水事故模拟分析

华北电力大学a.核热工安全与标准化研究所；b.非能动核能安全技术北京市重点实验室，北京〓102206

出版日期:2016-01-25

Simulation analysis of small break loss of coolant accident of AP1000 power unit

North China Electric Power University，a.Institute of Nuclear Thermal hydraulic Safety and Standardization; b. Beijing Key Laboratory for Passive Safety Technology of Nuclear Energy,Beijing 102206,China

Published:2016-01-25

摘要/Abstract

摘要：

摘要：采用美国MST公司核事故仿真软件PCTRAN，对AP1000小破口失水事故进行瞬态曲线分析，仿真结果表明：当发生400cm²小破口失水事故后,AP1000机组堆芯补水箱和堆芯安注箱水位随反应堆系统压力下降而下降，反应堆系统压力降到13.09MPa 时，触发AP1000机组非能动余热排出系统热交换器导出堆芯余热；当反应堆系统的压力降到1.52MPa时，堆芯水位开始上升；到反应堆系统压力达到0.29MPa 后，压力开始趋于稳定。计算后的反应堆系统压力在数值上与西屋公司用NOTRUMP软件分析的结果大致一样。

关键词: 关键词：AP1000机组, 小破口失水事故, PCTRAN软件, 瞬态曲线, 模拟分析

Abstract:

Abstract:Using the nuclear accident simulation software PCTRAN of MST Company, this paper carried out a transient curve analysis of small break loss of coolant accident (SBLOCA) of AP1000 power unit.The simulation results are as follows:After the occurrence of 400 cm² SBLOCA of AP1000 power unit,the water levels of makeup tank and safety injection tank of reactor core fall with the pressure decrease of reactor system. When the pressure drops to 13.09 MPa,the heat exchanger of passive residual heat removal system is triggered to remove the residual heat of reactor core.When the pressure continues to drop to 1.52 MPa,the water level of reactor core begins to rise.After the pressure reaches to 0.29MPa,it begins to be stabilizing.The calculated system pressure is in concordance with the results that obtained using the software NOTRUMP by Westinghouse Corporation in time and number.

Key words: Keywords:AP1000 power unit, small break loss of coolant accident, PCTRAN, transient curve, simulation analysis

陈杰，周涛，刘亮，李宇. AP1000机组小破口失水事故模拟分析[J]. 华电技术, 2016, 38(1): 68-71.

CHEN Jie, ZHOU Tao, LIU Liang, LI Yu. Simulation analysis of small break loss of coolant accident of AP1000 power unit[J]. Huadian Technology, 2016, 38(1): 68-71.

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