

浏览全部资源
扫码关注微信
环境保护部核与辐射安全中心 北京 100082
Received:19 April 2017,
Revised:26 June 2017,
Published:10 December 2017
移动端阅览
Lei LEI, Jianping JING, Xuedong QIAO, et al. Analysis of the key factors in passive containment cooling system based on CERT[J]. Nuclear techniques, 2017, 40(12): 120603
Lei LEI, Jianping JING, Xuedong QIAO, et al. Analysis of the key factors in passive containment cooling system based on CERT[J]. Nuclear techniques, 2017, 40(12): 120603 DOI: 10.11889/j.0253-3219.2017.hjs.40.120603.
非能动安全壳冷却系统(Passive Containment Cooling System,PCS)是第三代非能动反应堆的专设安全系统之一,用于在事故情况下导出安全壳内热量。基于非能动安全壳冷却系统综合性能试验台架(Containmentsafety vErification
via
integRal Test,CERT),本文研究影响PCS系统冷却效果的关键因素。采用安全壳分析程序针对CERT试验台架进行建模和计算,将计算结果与试验结果进行了对比验证。在此基础上模拟了冷管段双端断裂事故喷放下的试验壳内压力响应,并对壳外冷却水流量、壳外冷却水膜覆盖率、环腔风速等关键参数进行了敏感性分析。结果表明,冷却剂丧失事故(Loss Of Coolant Accident,LOCA)工况下,壳内压力经历两个峰值后逐渐降低,峰值压力0.266 1 MPa。壳外冷却水流量、水膜覆盖率对冷却效果影响显著,二者的降低将造成壳内压力的升高;环腔风速的增大有一定的降压作用。
Background
2
Passive containment cooling system (PCS) is part of the passive reactor safety design for cooling down the containment in accidents.
Purpose
2
This study aims to analyze the key factors affecting the cooling capacity of PCS based on the containment safety verification
via
integral test (CERT).
Methods
2
The calculating model of CERT was established using containment safety analysis program. The calculating results and the experiment results were compared to verify the model. The inner containment pressure response of double-ended cold leg guillotine (DECLG) break accident was calculated and the sensitive analysis of some parameters such as the cooling water flow
the outer shell cooling water coverage and the annulus wind speed were performed.
Results
2
The result showed that the calculated pressure and temperature were similar to the experimental test results with a little bit higher than the latter. The maximum pressure of DECLG is 0.266 1 MPa. The inner containment pressure increased significantly when the cooling water flow and the outer shell cooling water coverage decreased. The pressure decreased slightly when the annulus wind speed increased.
Conclusion
2
The calculating model is applicable for CERT calculations
and the results are conservative. Inner containment pressure is sensitive to the cooling water flow and the outer shell cooling water coverage.
温丽晶. 非能动安全壳冷却系统导热能力裕度验证试验任务书[R]. 北京: 环境保护部核与辐射安全中心, 2016.
WEN Lijing. PCS cooling capacity margin test mission file[R]. Beijing:Nuclear and Radiation Safety Center, 2016.
石 兴伟 , 雷 蕾 , 兰 兵 , . PCS表面液膜覆盖率对安全壳完整性影响分析 . 核技术 , 2017 . 40 ( 1 ): 010602 DOI: 10.11889/j.0253-3219.2017.hjs.40.010602 http://doi.org/10.11889/j.0253-3219.2017.hjs.40.010602 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract704.shtml .
Xingwei SHI , Lei LEI , Bing LAN , . The influence analysis of PCS surface liquid film coverage on the containment integrity . Nuclear Techniques , 2017 . 40 ( 1 ): 010602 DOI: 10.11889/j.0253-3219.2017.hjs.40.010602 http://doi.org/10.11889/j.0253-3219.2017.hjs.40.010602 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract704.shtml .
叶 成 . APl000核电站非能动安全系统的比较优势 . 原子能科学技术 , 2012 . 46 ( 10 ): 1221 - 1225 . http://kns.cnki.net/KCMS/detail/detail.aspx?filename=yzjs201210015&dbname=CJFD&dbcode=CJFQ .
Cheng YE . Comparative advantages of AP1000 passive safety system . Atomic Energy Science and Technology , 2012 . 46 ( 10 ): 1221 - 1225 . http://kns.cnki.net/KCMS/detail/detail.aspx?filename=yzjs201210015&dbname=CJFD&dbcode=CJFQ .
叶 成 , 倪 陈宵 . APl000非能动安全壳冷却水WGOTHIC分析 . 原子能科学技术 , 2013 . 47 ( 12 ): 2225 - 2230 . DOI: 10.7538/yzk.2013.47.12.2225 http://doi.org/10.7538/yzk.2013.47.12.2225 .
Cheng YE , Chenxiao NI . WGOTHIC analysis on AP1000 passive containment cooling water . Atomic Energy Science and Technology , 2013 . 47 ( 12 ): 2225 - 2230 . DOI: 10.7538/yzk.2013.47.12.2225 http://doi.org/10.7538/yzk.2013.47.12.2225 .
韦 胜杰 . 竖壁降液膜流动纵向及水平发展规律研究 . 原子能科学技术 , 2013 . 47 ( 2 ): 213 - 217 . DOI: 10.7538/yzk.2013.47.02.0213 http://doi.org/10.7538/yzk.2013.47.02.0213 .
Shengjie WEI . Horizontal and longitudinal characteristics of water film falling on vertical plate . Atomic Energy Science and Technology , 2013 . 47 ( 2 ): 213 - 217 . DOI: 10.7538/yzk.2013.47.02.0213 http://doi.org/10.7538/yzk.2013.47.02.0213 .
刘 晶晶 , 王 成章 , 徐 志新 . 安全壳内置换料水箱子系统设计改进的PSA评价 . 核技术 , 2015 . 38 ( 9 ): 090605 DOI: 10.11889/j.0253-3219.2015.hjs.38.090605 http://doi.org/10.11889/j.0253-3219.2015.hjs.38.090605 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract467.shtml .
Jingjing LIU , Chengzhang WANG , Zhixin XU . Probabilistic safety analysis of design improvement of IRWST sub-system . Nuclear Techniques , 2015 . 38 ( 9 ): 090605 DOI: 10.11889/j.0253-3219.2015.hjs.38.090605 http://doi.org/10.11889/j.0253-3219.2015.hjs.38.090605 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract467.shtml .
朱 继洲 , 奚 树人 , 单 建强 , . 核反应堆安全分析 , : 西安 西安交通大学出版社 , 2004 . 106 - 127 .
Jizhou ZHU , Shuren XI , Jianqiang SHAN , . Nuclear reactor safety analysis , : Xi'an Xi'an Jiaotong University Press , 2004 . 106 - 127 .
叶 成 , 郑 明光 , 王 勇 , . APl000安全壳厚度对传热性能的影响 . 原子能科学技术 , 2014 . 48 ( 3 ): 458 - 461 . http://kns.cnki.net/KCMS/detail/detail.aspx?filename=yzjs201403014&dbname=CJFD&dbcode=CJFQ .
Cheng YE , Mingguang ZHENG , Yong WANG , . Effect of APl000 steel containment thickness on heat transfer performance . Atomic Energy Science and Technology , 2014 . 48 ( 3 ): 458 - 461 . http://kns.cnki.net/KCMS/detail/detail.aspx?filename=yzjs201403014&dbname=CJFD&dbcode=CJFQ .
B Sutharshan , M Mutyala , R P Vijuk , . The AP1000 reactor:passive safety and modular design . Energy Procedia , 2011 . 1 ( 1 ): 293 - 302 . http://www.sciencedirect.com/science/article/pii/S1876610211015475 .
Nuclear Regulatory Commission. Final safety evaluation report for AP1000 related to certification of the AP1000 standard design[R]. Chapter 19. Washington DC:Nuclear Regulatory Committee, 2004.
0
Views
23
下载量
0
CSCD
Publicity Resources
Related Articles
Related Author
Related Institution
京公网安备11010802024621