CPR1000核电厂SGTR事故长期阶段的分析研究
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摘要
对于蒸汽发生器传热管破裂事故,现有的分析主要是计算对于环境的释放量,并分析至一、二回路压力平衡,而未对冷却至安全停堆状态进行研究。SGTR长期分析采用CATHARE程序以原有瞬态分析为基础,将分析拓展至安全停堆状态,并额外地考虑丧失厂外电和一些非安全级系统不可用情况下的事故处理策略。分析结果表明:对于我国的CPR1000系列堆型,与SGTR短期阶段不同,在事故长期阶段的分析中对事故的缓解必须考虑非安全级系统或设备的投入,这就与设计基准事故分析的保守性要求不符。本文为此对我国CPR1000系列核电厂提出管理建议。
For the steam generator tube rupture( SGTR) accident,the existing analysis is mainly to calculate the release amount of radiation to the environment,only to analyze the pressure balance of the primary and secondary loop,but not to the further cooling to the safe shutdown state. SGTR long term analysis uses the CATHARE code to extend the analysis to safe shutdown state based on the transient analysis. And additionally,the loss of offsite power( LOOP) and some non-safety system availability are considered in case of accident treatment strategies. The results show that: for the CPR1000 series plants in China,different from the short-term stage of SGTR,it is necessary to consider the effects of the non-safety system or equipment in the analysis of the long term accident,which is inconsistent with the conservative requirements of the design basis accident analysis. Accordingly,some management suggestions for CPR1000 series nuclear power plants in China are put forward to strengthen the weak link.
For the steam generator tube rupture( SGTR) accident,the existing analysis is mainly to calculate the release amount of radiation to the environment,only to analyze the pressure balance of the primary and secondary loop,but not to the further cooling to the safe shutdown state. SGTR long term analysis uses the CATHARE code to extend the analysis to safe shutdown state based on the transient analysis. And additionally,the loss of offsite power( LOOP) and some non-safety system availability are considered in case of accident treatment strategies. The results show that: for the CPR1000 series plants in China,different from the short-term stage of SGTR,it is necessary to consider the effects of the non-safety system or equipment in the analysis of the long term accident,which is inconsistent with the conservative requirements of the design basis accident analysis. Accordingly,some management suggestions for CPR1000 series nuclear power plants in China are put forward to strengthen the weak link.
引文
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[2]邢继,于沛,李军.华龙一号SGTR事故缓解措施及事故处理[J].核动力工程.2016,37(4):58-62.
[3]林萌,苏云,胡锐,等.核电站工程模拟器用于SGTR事故仿真分析研究[J].原子能科学技术,2005(3):240-245.
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[5]肖三平,叶杰,钱辉,等.AP1000核电厂SGTR事故工况下CMT水位分析[J].核安全,2014,13(3):45-49.
[6]毛家祥,刘全友,杨加东,等.核电厂蒸汽发生器传热管破裂事故处理[J].科技视界,2015(5):294+328.
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[11]詹文辉.SGTR事故二次侧安全阀卡开后的降温降压分析[J].核技术,2010,33(2):98-100.
[12]郑华.EPR缓解SGTR事故的设计特点[J].核科学与工程,2010,30(1):15-18.
[13]Sui Danting,Lu Daogang,Shang Changzhong,et al.Investigation on response of HPR1000 under different mitigation strategies after SGTR accident[J].Annals of Nuclear Energy,2018,112:328-336.
[14]石俊英.WWER-1000型核电站SGTR事故分析[J].核动力工程,2002,23(2):51-55.
[15]柯晓.CAP1000核电厂全功率范围SGTR事故研究[J].原子能科学技术,2014,48(6):1031-1037.
[16]袁明豪,冯雷,周拥辉,等.AP1000核电厂蒸汽发生器传热管破裂事故的分析研究[J].核安全.2009(4):37-41.
[17]刘耀华.AP1000堆型SGTR事故应对策略研究[D].保定:华北电力大学,2016.
[2]邢继,于沛,李军.华龙一号SGTR事故缓解措施及事故处理[J].核动力工程.2016,37(4):58-62.
[3]林萌,苏云,胡锐,等.核电站工程模拟器用于SGTR事故仿真分析研究[J].原子能科学技术,2005(3):240-245.
[4]李吉根,俞尔俊,戴传曾.秦山核电厂SGTR事故及其处置研究[J].核科学与工程,1996(3):193-199.
[5]肖三平,叶杰,钱辉,等.AP1000核电厂SGTR事故工况下CMT水位分析[J].核安全,2014,13(3):45-49.
[6]毛家祥,刘全友,杨加东,等.核电厂蒸汽发生器传热管破裂事故处理[J].科技视界,2015(5):294+328.
[7]郭城.核电厂蒸汽发生器传热管断裂事故运行管理[J].核动力工程.2013,34(2):107-110.
[8]俞尔俊,李吉根.《核电厂核安全》[M].北京:原子能出版社,2010.
[9]EDF.Design And Construction Rules For System Design Of900MWe PWR Nuclear Power Plants,RCC-P[S].Paris:EDF,1995.
[10]韩世超,赵嘉明,王翠芸,等.某核电堆型蒸汽发生器排污系统设计改进[J].南方能源建设,2016,3(3):45-47+53.
[11]詹文辉.SGTR事故二次侧安全阀卡开后的降温降压分析[J].核技术,2010,33(2):98-100.
[12]郑华.EPR缓解SGTR事故的设计特点[J].核科学与工程,2010,30(1):15-18.
[13]Sui Danting,Lu Daogang,Shang Changzhong,et al.Investigation on response of HPR1000 under different mitigation strategies after SGTR accident[J].Annals of Nuclear Energy,2018,112:328-336.
[14]石俊英.WWER-1000型核电站SGTR事故分析[J].核动力工程,2002,23(2):51-55.
[15]柯晓.CAP1000核电厂全功率范围SGTR事故研究[J].原子能科学技术,2014,48(6):1031-1037.
[16]袁明豪,冯雷,周拥辉,等.AP1000核电厂蒸汽发生器传热管破裂事故的分析研究[J].核安全.2009(4):37-41.
[17]刘耀华.AP1000堆型SGTR事故应对策略研究[D].保定:华北电力大学,2016.