压水堆核电站燃料厂房核燃料转运系统的抗震分析
|
摘要
压水堆核电站燃料厂房核燃料转运系统是压水堆核电站燃料厂房的主要核燃料操作设备,对其在地震工况下进行强度评定对保障核电站安全运行具有重要的意义。本文通过对百万千瓦级核电站燃料厂房核燃料转运系统进行有限元建模,针对该系统设备在异常工况(OBE)和事故工况(SSE)下的动力特性进行计算;考虑地震工况下自重条件的不利影响,对大车横梁、小车横梁、吊桥及其车架等主要构件进行了整体应力分析,对螺栓、焊缝和指形钩等关键部位进行了局部应力分析。依据RCC-M规范对该系统设备的整体及局部构件进行了强度评定,结果表明燃料厂房核燃料转运系统各构件的强度均满足抗震要求。
The spent fuel pit crane(SFPC)is a key equipment for fuel transfer inPWR nuclear power plant.The strength assessment for the crane structure and major components are important to ensure the safety in nuclear power plant operation under seismic conditions.In this study,ANSYS is adopted to construct the finite element model of the crane for a 1000 MWe nuclear power plant.The structural responses are computed under abnormal(OBE)and accident(SSE)conditions respectively.The internal forces and stresses are obtained with the method of square root of square sum(SRSS)under three different directions of seismic response spectrum.Considering the negative effects of the gravity,the strengths of main structures,such as beams of large and small carts,hanging bridge and its frames,are analyzed.Moreover,the local stresses of bolts,weld seams and finger shaped hook are also computed.Based on the RCC-M code,the strengths of global and local components are assessed.The results show that SFPC structures are in safety with good anti-seismic capability.
The spent fuel pit crane(SFPC)is a key equipment for fuel transfer inPWR nuclear power plant.The strength assessment for the crane structure and major components are important to ensure the safety in nuclear power plant operation under seismic conditions.In this study,ANSYS is adopted to construct the finite element model of the crane for a 1000 MWe nuclear power plant.The structural responses are computed under abnormal(OBE)and accident(SSE)conditions respectively.The internal forces and stresses are obtained with the method of square root of square sum(SRSS)under three different directions of seismic response spectrum.Considering the negative effects of the gravity,the strengths of main structures,such as beams of large and small carts,hanging bridge and its frames,are analyzed.Moreover,the local stresses of bolts,weld seams and finger shaped hook are also computed.Based on the RCC-M code,the strengths of global and local components are assessed.The results show that SFPC structures are in safety with good anti-seismic capability.
引文
[1]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.
[2]Nakamura N,Akitab S,Suzukic T,et al.Study of ultimate seismic response and fragility evaluation of nuclear power building using nonlinear three-dimensional finite element model[J].Nuclear Engineering and Design,2010,240:166-180.
[3]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.
[4]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.
[5]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.
[6]Zhang Z,He S,Xu M.Seismic analysis of liquid storage container in nuclear reactors[J].Nuclear Engineering and Design,2007,237:1325-1331.
[7]余华金,张双旺,栾霖.核安全三级容器应力分析评定[J].原子能科学技术,2002,36(2):137-142.
[8]压力堆核电机械设备设计和建造规范[S].RCC-M 2000版,H篇,附录ZVI.
[9]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
[2]Nakamura N,Akitab S,Suzukic T,et al.Study of ultimate seismic response and fragility evaluation of nuclear power building using nonlinear three-dimensional finite element model[J].Nuclear Engineering and Design,2010,240:166-180.
[3]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.
[4]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.
[5]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.
[6]Zhang Z,He S,Xu M.Seismic analysis of liquid storage container in nuclear reactors[J].Nuclear Engineering and Design,2007,237:1325-1331.
[7]余华金,张双旺,栾霖.核安全三级容器应力分析评定[J].原子能科学技术,2002,36(2):137-142.
[8]压力堆核电机械设备设计和建造规范[S].RCC-M 2000版,H篇,附录ZVI.
[9]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
版权所有：© 2023 中国地质图书馆 中国地质调查局地学文献中心