M310核电站非能动安全改进措施研究
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摘要
本文利用MELCOR1.8.5程序建立了典型的M310核电站的严重事故模型,基于该模型设计了多种非能动的缓解措施,针对由全厂断电诱发的严重事故,模拟研究了这些非能动安全措施的缓解效果。研究结果表明:在全厂断电事故下,堆芯补水箱系统、堆腔注水系统、非能动余热排出系统均能有效地投入使用,并显著地延缓事故的发展,将核电站稳定在一个安全的状态,为人工干预赢得更多时间。
A severe accident model of typical M310 nuclear power station with MELCOR 1.8.5code was constructed in this paper.Based on the model,several passive safety measures were designed,and their benefits of mitigating the accident caused by station blackout(SBO)were simulated.The calculating results show that the core makeup tank system,external reactor vessel cooling system and passive residual heat removal system can operate successfully in SBO,postpone the progression of the accident markedly,stabilize the M310 nuclear power station in a safe state and gain more time for manual intervention.
A severe accident model of typical M310 nuclear power station with MELCOR 1.8.5code was constructed in this paper.Based on the model,several passive safety measures were designed,and their benefits of mitigating the accident caused by station blackout(SBO)were simulated.The calculating results show that the core makeup tank system,external reactor vessel cooling system and passive residual heat removal system can operate successfully in SBO,postpone the progression of the accident markedly,stabilize the M310 nuclear power station in a safe state and gain more time for manual intervention.
引文
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[6]郎明刚.大亚湾核电厂全厂断电事故裂变产物行为计算[J].核科学与工程,2002,22(4):339-341.LANG Minggang.Calculation of fission product behaviour in a station blackout accident of Daya Bay Nuclear Power Plant[J].Chinese Journal of Nuclear Science and Engineering,2002,22(4):339-341(in Chinese).
[7]林诚格.非能动安全先进核电厂AP1000[M].1版.北京:原子能出版社,2008.
[8]王建伟.AP1000与M310堆型余热排出系统的差异分析[J].核动力工程,2009,30(6):11-14.WANG Jianwei.Analysis of differences between residual heat removal systems in AP1000 and M310[J].Nuclear Power Engineering,2009,30(6):11-14(in Chinese).
[9]YONOMOTO T,KUKITA Y,SCHULTZ R R.Heat transfer analysis of the passive residual heat removal system in ROSA/AP600 experiments[J].Nuclear Technology,1998,124(1):18-30.
[10]袁添鸿,于雷,王川.全厂断电事故下AP1000非能动余热排出系统分析[J].原子能科学技术,2010,44(增刊):248-252.YUAN Tianhong,YU Lei,WANG Chuan.Research on passive residual heat remove system under loss of power[J].Atomic Energy Science and Technology,2010,44(Suppl.):248-252(in Chinese).
[2]JUHN P E,KUPITZ J,CLEVELAND J.IAEA activities on passive safety systems and overview of international development[J].Nuclear Engineering and Design,2000,201:41-59.
[3]MELCOR computer code manuals,NUREG/CR-6119[R].USA:Sandia National Laboratories,2000.
[4]广东核电培训中心.900 MW压水堆核电站系统与设备[M].北京:原子能出版社,2005.
[5]魏玮.中国压水堆核电站堆芯损伤评价研究[D].北京:清华大学核能与新能源技术研究院,2008.
[6]郎明刚.大亚湾核电厂全厂断电事故裂变产物行为计算[J].核科学与工程,2002,22(4):339-341.LANG Minggang.Calculation of fission product behaviour in a station blackout accident of Daya Bay Nuclear Power Plant[J].Chinese Journal of Nuclear Science and Engineering,2002,22(4):339-341(in Chinese).
[7]林诚格.非能动安全先进核电厂AP1000[M].1版.北京:原子能出版社,2008.
[8]王建伟.AP1000与M310堆型余热排出系统的差异分析[J].核动力工程,2009,30(6):11-14.WANG Jianwei.Analysis of differences between residual heat removal systems in AP1000 and M310[J].Nuclear Power Engineering,2009,30(6):11-14(in Chinese).
[9]YONOMOTO T,KUKITA Y,SCHULTZ R R.Heat transfer analysis of the passive residual heat removal system in ROSA/AP600 experiments[J].Nuclear Technology,1998,124(1):18-30.
[10]袁添鸿,于雷,王川.全厂断电事故下AP1000非能动余热排出系统分析[J].原子能科学技术,2010,44(增刊):248-252.YUAN Tianhong,YU Lei,WANG Chuan.Research on passive residual heat remove system under loss of power[J].Atomic Energy Science and Technology,2010,44(Suppl.):248-252(in Chinese).