[1]吴鹏,刘宇生,王冠一,等.CPR1000机组满功率运行发生严重事故后缓解举措有效性研究[J].应用科技,2020,47(6):84-89.[doi:10.11991/yykj.202001008]
　WU Peng,LIU Yusheng,WANG Guanyi,et al.Effectiveness research about mitigation measures of serious nuclear accidents on RP mode of CPR1000 unit[J].Applied science and technology,2020,47(6):84-89.[doi:10.11991/yykj.202001008]
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《应用科技》[ISSN:1009-671X/CN:23-1191/U]

卷:
第47卷
期数:
2020年6期
页码:
84-89
栏目:
核科学技术与应用
出版日期:
2021-01-31

文章信息/Info

Title:
Effectiveness research about mitigation measures of serious nuclear accidents on RP mode of CPR1000 unit
作者:
吴鹏;  刘宇生;  王冠一;  贾伟
生态环境部 核与辐射安全中心，北京 100082
Author(s):
WU Peng;  LIU Yusheng;  WANG Guanyi;  JIA Wei
Nuclear and Radiation Safety Center, Ministry of Environmental Protection, Beijing 100082, China
关键词:
核电站; 严重事故; 福岛核电站核事故; 缓解举措; 有效性; 满功率运行模式; 事故序列; 事故进程
Keywords:
nuclear power plant; severe accident; Fukushima nuclear accident; mitigation measures; effectiveness; RP mode; accident sequence; accident progress
分类号:
TL339
DOI:
10.11991/yykj.202001008
文献标志码:
A
摘要:
为对严重事故管理导则(SAMG)的编写和实施做进一步改进，本文在调研国内其他核电厂严重事故后缓解有效举措后，选择冷却剂主管道冷段部分双端断裂(LBLOCA)叠加丧失应急堆芯冷却(无高、低安注投入，无安全壳主/辅喷淋)、主蒸汽管道断裂(MSLB)叠加丧失喷淋、失水(LOFW)未能紧急停堆的预期瞬态(ATWS)严重事故状态等作为CPR1000机组的最重要的严重事故的事故序列，利用核与辐射安全中心全范围验证仿真模拟机包含严重事故发生情况下的仿真验证系统(VVS)，在严重事故发生后，实时跟踪采取缓解举措与未采取缓解举措事故的发展后果，从而验证CPR1000核电机组满功率运行时(RP模式)，严重事故发生后SAMG缓解举措的有效性，为CPR1000机组SAMG的改进提供借鉴。仿真结果表明，采取SAMG缓解举措，能够有效抑制严重事故的进一步恶化。
Abstract:
After the Fukushima nuclear accident, regulatory authorities have put forward requirements for the severe accident management guideline (SAMG). Based on the investigation of serious accident mitigation measures of other nuclear power units in China, we selected loss of cooling water accident caused by large breach (LBLOCA) and loss of the emergency core cooling system (without high and low safety injection inputs and no containment spray), large breach of the main steam pipe (MSLB) and loss of flow water supply and anticipated transients without scram (ATWS) as the relatively important serious accident sequences for the CPR1000 unit. Using the virtual verification simulation system (VVS) of the Nuclear and Radiation Safety Center system to analyze and compare the development of serious accidents with and without mitigation measures. This paper aims to verify the effectiveness about SAMG (RP Mode) of CPR1000 unit after serious accident. In the end, we provide a reference for the improvement of SAMG on CPR1000 unit. The results show that the implementation of the SAMG about CPR1000 unit can inhibit the development of severe accidents.

参考文献/References:

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备注/Memo

备注/Memo:
收稿日期:2019-12-26。
作者简介:吴鹏，男，工程师;刘宇生，男，工程师
通讯作者:刘宇生，E-mail：liuyusheng8866@163.com
更新日期/Last Update: 2021-02-05