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中国超临界水堆完全失流事故分析

Analysis of Complete Loss of Forced Flow Accident in China Super-Critical Water Reactor

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【作者】 张丹鲁剑超刘松涛单建强

【Author】 ZHANG Dan1,LU Jian-chao1,LIU Song-tao1,SHAN Jian-qiang2 1.Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610041,China;2.Xi’an Jiao Tong University,Xi’an,710049,China

【机构】 中国核动力研究设计院核反应堆系统设计技术国家级重点实验室西安交通大学

【摘要】 中国超临界水堆(CSR1000)由于系统采用直接循环方式,给水流量或厂外交流电的丧失将导致系统发生失流事故。堆芯双流程设计导致堆芯在失流事故中面临流量反转问题,失流事故成为威胁堆芯安全的重要典型事故。本文采用仿真程序APROS对CSR1000冷却剂系统(RCS)和相关安全系统建模,分析CSR1000在完全失流事故下的堆芯热工-水力学性能。分析表明,在失流事故短期阶段,高压给水箱可缓解事故;长期阶段,非能动余热排出系统(PRHR)的投入能使堆芯维持在安全状态。

【Abstract】 China supercritical water reactor(CRS1000) was developed by NPIC,which has pressure vessel,double flow pass core,and directly cycle loop.As these characteristics,loss of feed water or loss of offsite power will cause the complete loss of forced flow accident,and the first pass core will encounter flow reversal course during the accident,which make the LOFA(Loss Of forced Flow Accident) become the more serious accident in CRS1000.The CRS1000 system model was created by APROS,and LOFA was analyzed by this model.The result shows that,during the short time of LOFA,the operation of HFT(High pressure Feed water Tank) will mitigate the accident,and in long time,the PRHR(Passive Residual Heat Removal system) will function and make the core at the safety condition.

【关键词】 中国超临界水堆完全失流APROS非能动
【Key words】 CRS1000Complete loss of forced flowAPROSPassive
  • 【文献出处】 核动力工程 ,Nuclear Power Engineering , 编辑部邮箱 ,2013年01期
  • 【分类号】TL364.4
  • 【被引频次】3
  • 【下载频次】290
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