压水堆核电站燃料传输系统抗震性能有限元分析
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摘要
压水堆核电站燃料传输系统的主要功能是将核燃料组件在反应堆厂房和燃料厂房之间进行相互传送。为保障其结构在不同工况下能够安全运行,需对其在异常工况(OBE)和事故工况(SSE)下进行抗震性能分析。为此,采用有限元分析软件ANSYS 12.0对某百万千瓦级核电站的燃料传输系统进行了结构建模;对传输系统在运行过程中不同构型下的转运通道、承载器、传输小车、反应室倾翻架、燃料室倾翻架、燃料室轨道结构和反应室轨道结构等主要构件在不同工况下进行了应力分析;采用SRSS方法进行了应力组合,并依据RCCM规范对各构件进行不同工况下的强度评定。结果表明,在异常和事故工况下,燃料传输系统在不同构型下各结构均满足强度要求,具有良好的抗震性能。
In the PWR nuclear power plant,the function of the fuel transfer system(FTS) is to transfer the fuel assembly between the reactor building and the fuel building.The seismic analysis of the transfer system structure should be carried out to ensure the safety under OBE and SSE.Therefore,the ANASYS 12.0 software is adopted to construct the finite element analysis model for the fuel transfer system in a million kilowatt nuclear power plant.For the various configurations of FTS in the operating process,the stresses of the main structures,such as the transfer tube,fuel assembly container,fuel conveyor car,lifting frame in the reactor building,lifting frame in the fuel building,support and guide structure of conveyor car and the lifting frame in both buildings,are computed.The stresses are combined with the method of square root of square sum(SRSS) and assessed under various seismic conditions based on RCCM code,the results of the assessment satisfy the code.The results show that the stresses of the fuel transfer system structure meet the strength requirement,meanwhile,it can withstand the earthquake well.
In the PWR nuclear power plant,the function of the fuel transfer system(FTS) is to transfer the fuel assembly between the reactor building and the fuel building.The seismic analysis of the transfer system structure should be carried out to ensure the safety under OBE and SSE.Therefore,the ANASYS 12.0 software is adopted to construct the finite element analysis model for the fuel transfer system in a million kilowatt nuclear power plant.For the various configurations of FTS in the operating process,the stresses of the main structures,such as the transfer tube,fuel assembly container,fuel conveyor car,lifting frame in the reactor building,lifting frame in the fuel building,support and guide structure of conveyor car and the lifting frame in both buildings,are computed.The stresses are combined with the method of square root of square sum(SRSS) and assessed under various seismic conditions based on RCCM code,the results of the assessment satisfy the code.The results show that the stresses of the fuel transfer system structure meet the strength requirement,meanwhile,it can withstand the earthquake well.
引文
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[2]压力堆核电机械设备设计和建造规范[S].RCC-M2000版,H篇,附录ZVI.
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[11]GB50267—97[S],核电厂抗震设计规范,1997.
[12]张熠,钱江.核电站安全阀结构抗震性能分析及评定[J].工程抗震与加固改造,2009,31(6):113-115.
[2]压力堆核电机械设备设计和建造规范[S].RCC-M2000版,H篇,附录ZVI.
[3]洪景丰.核电厂地震分析综述[J].核动力工程,1996,17(3):193-198.
[4]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.
[5]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.
[6]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.
[7]Zhang Z,He S,Xu M.Seismic analysis of liquid storagecontainer in nuclear reactors.Nuclear Engineering andDesign[J],2007,237:1325-1331.
[8]Sinha J K.Simplified method for the seismic qualificationusing measured modal data.Nuclear Engineering andDesign[J],2003,224:125-129.
[9]李建丰,徐鸿,王楠,等.设备地震响应的频谱分析法[J].北京化工大学学报,2003,30(1):57-60.
[10]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.
[11]GB50267—97[S],核电厂抗震设计规范,1997.
[12]张熠,钱江.核电站安全阀结构抗震性能分析及评定[J].工程抗震与加固改造,2009,31(6):113-115.
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