循环水浸泡影响下的新型地坑过滤器抗震分析
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摘要
安全壳地坑过滤器是核电厂专用的重要安全设施,用于在失水事故(LOCA)下收集安全壳内的泄漏水和喷淋水,以便再循环使用,从而保证安注泵和喷淋系统不被杂质损坏。为了对新型地坑过滤器结构的抗震性能进行分析,以其中的典型模块为例,采用ANSYS软件进行数值建模,并针对其在不同工况下进行了应力分析;地坑过滤器结构的附加水质量通过经验公式和试验的方法得到,在抗震分析中考虑了地坑过滤器结构周围流体对结构抗震性能的影响;并依据RCC-M规范对过滤器的滤筒和汇流槽进行了应力强度评定。该模块的计算结果表明,在不同工况下该新型安全壳地坑过滤器具有良好的抗震性能,满足规范的对强度的要求。
The sump filter is an important and exclusive safety facility in nuclear power plants. Its function is to collect the leaked water and sprayed water in containment vessel under LOCA condition. The collected water can be used periodically to avoid the damage of injection pump and spray system with impurity. In this paper,the typical module is chosen as an example to be analyzed using finite element model with ANSYS software. The stresses are analyzed under different conditions. The influence of additional water is decided by experience formula and relevant test. In the seismic analysis,the influence of the fluid around the structure has been considered. Based on the RCC-M Code,the strengths of cartridge and shell structure of the sump filter are assessed. The results show that the new type of sump filter has perfect anti-seismic properties and can achieve the strength requirement.
The sump filter is an important and exclusive safety facility in nuclear power plants. Its function is to collect the leaked water and sprayed water in containment vessel under LOCA condition. The collected water can be used periodically to avoid the damage of injection pump and spray system with impurity. In this paper,the typical module is chosen as an example to be analyzed using finite element model with ANSYS software. The stresses are analyzed under different conditions. The influence of additional water is decided by experience formula and relevant test. In the seismic analysis,the influence of the fluid around the structure has been considered. Based on the RCC-M Code,the strengths of cartridge and shell structure of the sump filter are assessed. The results show that the new type of sump filter has perfect anti-seismic properties and can achieve the strength requirement.
引文
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[15]AFCEN.RCC-P,Design and construction rules for systemdesign of 900 MWe PWR nuclear plants[S].France:AFCEN,1991.
[2]钱浩,邓晶晶,徐定耿,等.安全壳再循环地坑过滤网应力分析[J].力学季刊,2007,28(1):165-169.
[3]Nuclear Power Engineering Committee.IEEE std 344-2004,IEEE recommended practice for seismic qualificationof Class 1E equipment for nuclear power generatingstations[R].New York:Nuclear Power EngineeringCommittee,2004.
[4]戚承志,钱七虎.核电站抗震研究综述[J].地震工程与工程振动,2000,20(3):76-86.
[5]王明弹,凌云,王晓雯,等.先进核电厂半球顶安全壳抗震分析[J].原子能科学技术,2008,42(S1):401-407.
[6]刘宇,张庆华,李春.核电厂安全壳地坑过滤网堵塞问题的机理分析[J].核安全,2008(3):52-56.
[7]李增光,王炯,吴天行.核电站环形吊车抗震计算分析[J].核动力工程,2008,29(1):46-49.
[8]NRC.NUREG/CR-6645,Reevaluation of regulatoryguidance on modal response combination methods forseismic response spectrum analysis[S].Washington D.C.:NRC,1999.
[9]国家地震局.中国国家标准核电厂抗震设计规范(GB50267-97)[R].北京:北京计划出版社,1997.
[10]Kostarev V V,Petrenko A V,Vasilyev P S.An advancedseismic analysis of an NPP powerful turbogenerator on anisolation pedestal[J].Nuclear Engineering and Design,2007(237):1315-1324.
[11]谭忠文,王海涛,何树延.核电厂大型组合结构的有限元抗震分析方法研究[J].核科学与工程,2008(2):188-192.
[12]崔赪昕.中广核岭澳电厂二期LOT150B-2冷水机组抗震力学分析及应力评定[J].原子能科学技术,2008,42(S):411-413.
[13]AFCEN.RCC-M,Design and construction rules formechanical components of PWR nuclear islands[S].France:AFCEN,2007.
[14]NRC.Regulatory Guide 1.61,Damping values for seismicdesign of nuclear power plants[S].Washington D.C.:NRC,2007.
[15]AFCEN.RCC-P,Design and construction rules for systemdesign of 900 MWe PWR nuclear plants[S].France:AFCEN,1991.
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