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压水堆核电站全厂断电事故及辅助给水系统的缓解能力研究
引用本文:张龙飞,张大发,王少明.压水堆核电站全厂断电事故及辅助给水系统的缓解能力研究[J].核动力工程,2007,28(3):98-102.
作者姓名:张龙飞  张大发  王少明
作者单位:海军工程大学核能科学与工程系,武汉,430033;海军工程大学核能科学与工程系,武汉,430033;海军工程大学核能科学与工程系,武汉,430033
基金项目:致谢:感谢美国INEEL的Chris博士对程序计算中遇到的技术问题给予指导和帮助.
摘    要:以美国surry核电站为参考对象,采用最佳估算程序SCDAP/RELAP5/MOD3.4,建立了一个典型的三环路压水堆核电站严重事故计算模型,对全厂断电(SBO)事故的物理现象及堆芯熔化进程进行了详细分析,并研究了全厂断电事故发生后辅助给水(AFW)分别持续1800s和3600s对事故的缓解效果.计算结果显示,辅助给水能有效地延缓堆芯熔化进程,大大推迟反应堆压力容器的失效时间,为操纵员恢复交流电源以及实施其它缓解措施赢得更多的时间.

关 键 词:严重事故  全厂断电  辅助给水  蠕变破裂失效
文章编号:0258-0926(2007)03-0098-05
修稿时间:2006-02-152006-09-20

Study on SBO Accident and Mitigating Capability of Auxiliary Feedwater System for PWR
ZHANG Long-fei,ZHANG Da-fa,WANG Shao-ming.Study on SBO Accident and Mitigating Capability of Auxiliary Feedwater System for PWR[J].Nuclear Power Engineering,2007,28(3):98-102.
Authors:ZHANG Long-fei  ZHANG Da-fa  WANG Shao-ming
Affiliation:Department of Nuclear Science and Engineering, Naval University of Engineering, Wuhan, 430033, China
Abstract:Using the best estimate computer code SCDAP/RELAP5/MOD3.4 and Surry NPP as reference object,a representative three loops PWR severe accident calculation model is established and station blackout(SBO) induced core melt progression and phenomenon is analyzed.Effects are discussed when auxiliary fe-edwater(AFW) operates to mitigate the SBO accident progression 1800s and 3600s after SBO starting.Cal-culation results show that core melt progression and failure time of reactor pressure vessel is greatly delayed,thus the operator has more time available for AC recovery and other mitigation measures to prevent reactor pressure vessel failure.
Keywords:Severe accident  Station blackout  Auxiliary feedwater  Creep rupture failure
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