Southwest University of Science and Technology本科毕业设计（论文）压水堆核电站全厂断电事故模拟研究学院名称国防科技学院专业名称核工程与核技术学生姓名学号指导教师二〇一三年五月压水堆核电站全厂断电事故模拟研究摘要：压水堆核电站全厂断电可能发展成为堆芯熔化的严重事故,并最终导致安全壳超压失效。
全厂断电事故中主泵轴封处可能会由于失去冷却而出现泄漏;如果此时一回路系统维持在安全阀设定压力的水平,可能会导致高压熔喷。
本论文主要研究关于如何推迟较压力壳下封头熔穿时间，避免高压熔喷,降低安全壳发生早期失效等问题，利用MELCOR程序分析研究严重核电厂全厂断电事故，研究表明全厂断电事故发生后，发电机带厂用电失败，主泵失电开始惰转，一回路冷却剂流量迅速下降，开始自然循环，堆芯由于得不到冷却剂补充，剩余冷却剂不断蒸发，液位迅速下降，堆芯出现沸腾并且开始裸露，逐渐融化，并最终导致安全壳发生超压失效。
最后通过对全厂断电事故发生时一回路系统热工水力响应、堆芯部件行为、安全壳内的热工水力现象进行分析，提出对核电厂严重事故的缓解措施。
关键词：全厂断电；严重事故；高压熔喷；热工水力响应；安全壳响应Analysis of station blackout accident in Pressurized waterreactors nuclear power plantsAbstract:nuclear power plant outage may develop into a water pressure core melt accident serious heap,and lead to vessel overpressure failure.The main pump power accident may be due to the cooling and the leakage loss;if a closed-loop system to maintain the safety valve set pressure,may lead to high pressure spray.This paper mainly studies how to turn ahead pressure vessel penetration time,avoid high pressure spray,reduce the control problem of early failure,using MELCOR program to a serious analysis of nuclear power outage,studies show,blackout,auxiliary power machine power,power of the main pump has been idle in sharp decline,coolant flow,began to natural circulation,reactor core coolant supply due to lack of,the remaining coolant evaporation,the water level dropped rapidly,nucleate boiling and naked,melting,and over pressure resulted from the failure of containment.When the accident occurred,the thermal-hydraulic response of a loop of the system,the core components of the behavior of power plant thermal hydraulic phenomena,containment,and analyzes the results,puts forward severe accident mitigation measures.Keywords:station blackout; severe accident;high pressure spray；The thermal-hydraulic response；containment response目录第一章前言 (1)第二章国内外对核电站研究现状 .................................................... 错误!未定义书签。
