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环境保护部核与辐射安全中心 北京 100082
Received:19 August 2016,
Revised:11 October 2016,
Published:2017-01
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Xingwei SHI, Lei LEI, Bing LAN, et al. The influence analysis of PCS surface liquid film coverage on the containment integrity[J]. Nuclear techniques, 2017, 40(1): 010602
Xingwei SHI, Lei LEI, Bing LAN, et al. The influence analysis of PCS surface liquid film coverage on the containment integrity[J]. Nuclear techniques, 2017, 40(1): 010602 DOI: 10.11889/j.0253-3219.2017.hjs.40.010602.
钢制安全壳是防止严重事故工况下放射性物质向环境释放的最后一道屏障,因此有必要研究分析事故条件下安全壳外液膜覆盖率对安全壳完整性影响,以得到安全壳在事故工况下的失效裕度。应用非能动安全壳分析程序,建立了大功率非能动反应堆非能动安全壳冷却系统(Passive Containment Cooling System,PCS)的热工水力模型,并以冷段双端剪切事故为基准研究对象,分别研究了水分配器单一故障和出水管堵管叠加水分配器故障两种事故工况。分析结果表明,两种事故工况在液膜覆盖率大于35%时,均不会出现短期安全壳超压超温失效;事故后24 h,液膜覆盖率低于45%时,安全壳出现长期冷却失效。此次研究得出结论:在流量大于61.76 m
3
·h
-1
、安全壳液膜覆盖率大于45%时,事故发生后24 h安全壳不会失效。
Background:
The containment is the last shielding to protect radioactive fission products under severe accident conditions from being released to the atmosphere.
Purpose:
In order to figure out the failure margin under accident conditions
it is necessary to research and analyze the effects of the surface liquid film coverage on the containment integrity for a Passive Containment Cooling System (PCS).
Methods:
The PCS thermal-hydraulic model has been built with passive containment analysis code in large power passive reactor. Based on the reference case of double ended guillotine (DEG) on a cold leg
both the water distribution tube failure and the spray pipe pluggage together with water distribution tube failure have been carried out
respectively.
Results:
The analysis results show that the containment will not fail due to overpressure and over temperature in short time in both failure cases when the water film coverage is larger than 35%
while it will fail in 24 h after accident when the results of the liquid film coverage is lower than 45%.
Conclusion:
It can be concluded that the containment will not fail in 24 h after accident with the liquid velocity greater than 61.76 m
3
·h
-1
and the liquid film coverage area greater than 45%.
邹 杰 , 佟 立丽 , 曹 学武 . 典型严重事故非能动安全壳冷却系统效果分析 . 原子能科学技术 , 2014 . 48 ( 增1 ): 362 - 368 . DOI: 10.7538/yzk.2014.48.S0.0362 http://doi.org/10.7538/yzk.2014.48.S0.0362 .
Jie ZOU , Lili TONG , Xuewu CAO . Assessment of passive containment cooling system performance during severe accident . Atomic Energy Science and Technology , 2014 . 48 ( Suppl 1 ): 362 - 368 . DOI: 10.7538/yzk.2014.48.S0.0362 http://doi.org/10.7538/yzk.2014.48.S0.0362 .
韦胜杰. 非能动安全壳冷却系统(PCCS)水膜流动行为及冷却能力实验研究[D]. 上海:上海交通大学, 2012.
WEI Shengjie. Experimental investigation on flow characteristics and heat transfer of falling water film of passive containment cooling system (PCCS)[D]. Shanghai:Shanghai Jiao Tong University, 2012.
叶 成 , 郑 明光 , 王 勇 , . AP1000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 . DOI: 10.7538/yzk.2014.48.03.0457 http://doi.org/10.7538/yzk.2014.48.03.0457 .
Cheng YE , Mingguang ZHENG , Yong WANG , . Effect of AP1000 steel containment thickness on heat transfer performance . Atomic Energy Science and Technology , 2014 . 48 ( 3 ): 458 - 461 . DOI: 10.7538/yzk.2014.48.03.0457 http://doi.org/10.7538/yzk.2014.48.03.0457 .
马 柏松 , 庄 亚平 , 郑 福涛 . 海阳核电一期工程严重事故下非能动安全壳冷却能力分析 . 核科学与工程 , 2014 . 34 ( 4 ): 530 - 536 . http://www.cnki.com.cn/Article/CJFDTOTAL-HKXY201404017.htm .
Baisong MA , Yaping ZHUANG , Futao ZHENG . Analysis for the passive containment cooling system of Haiyang NPP under severe accident condition . Nuclear Science and Engineering , 2014 . 34 ( 4 ): 530 - 536 . http://www.cnki.com.cn/Article/CJFDTOTAL-HKXY201404017.htm .
叶 成 , 郑 明光 , 王 勇 , . AP1000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 , Mingguang ZHENG , Yong WANG , . 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 .
王 国栋 . 应用GOTHIC8.0程序分析AP1000核电厂PCS传热传质过程 . 原子能科学技术 , 2015 . 49 ( 1 ): 83 - 88 . DOI: 10.7538/yzk.2015.49.01.0083 http://doi.org/10.7538/yzk.2015.49.01.0083 .
Guodong WANG . Analysis of heat and mass transfer process for AP1000 NPP PCS using GOTHIC8 . Atomic Energy Science and Technology , 2015 . 49 ( 1 ): 83 - 88 . DOI: 10.7538/yzk.2015.49.01.0083 http://doi.org/10.7538/yzk.2015.49.01.0083 .
Nuclear Regulatory Commission. Final safety evaluation report for AP1000 related to certification of the AP1000 standard design[R]. Chapter 3/6/19, Washington D C:Nuclear Regulatory Committee, 2004.
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