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| Analysis of spray pump casing security in 1 000 MW nuclear power plant |
| Wang Wenbo1, Liu Houlin1, Wang Kai1, Huang Haoqin1, Li Yongjin2 |
| 1.National Research Center of Pumps, Jiangsu University, Zhenjiang, Jiangsu 212013, China; 2.Yangzhou Changjiang River Pumps Co. Ltd., Yangzhou, Jiangsu 225200, China |
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Abstract Containment spray system is an essential facility for nuclear power plant safety, and spray pump is the core safety equipment in it. In order to study the security of spray pump, and verify it satisfies the anti-seismic standards, a spray pump in 1 000 MW nuclear power plant was chosen as the research object. First, pump casing modal analysis was conducted;then the anti-seismic calculation at operating basis earthquake seismic load and safe shutdown earthquake seismic load was performed; Finally thermal load was placed in the inner face of the pump, and thermal shock analysis was done. The results indicate that the fundamental frequency of the pump casing is 104.45 Hz, far more than 33 Hz, and its structure is rigid. The vibration direction of the structure is mainly horizontal. High thermal stress is located at the junction of pump frame and hull, while high seismic stress is located on heterogeneous parts in pump casing. The thermal deformation and seismic deformation are both located at the bottom. The maximum stress is far less than the allowable stress specified by ASMEⅡ. The pump satisfies the anti-seismic relevant standards.
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Received: 02 July 2014
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| [1]Birkhofer A. Seismic design of nuclear facilities in Germany [J]. Nuclear Engineering and Design, 1997, 172(6): 247-260.[2]Toshihiko Hirama,Masashi Goto,Hitoshi Kumagai. Seismic proof test of a reinforced concrete containment vessel(RCCV)part 3: Evaluation of seismic safety margin [J]. Nuclear Engineering and Design, 2007, 237(12): 1128-1139.[3]Kostarev V V, Petrenko A V, Vasilyev P S. An advanced seismic analysis of an NPP powerful turbogene-rator on an isolation pedestal[J]. Nuclear Engineering and Design, 2007, 237(12): 1315-1324.[4]李永安.西安脉冲堆抗震设计计算[J]. 核动力工程,2002,23(6):12-15. Li Yongan. Seismic design calculation of Xi′an pulsed reactor[J]. Nuclear Power Engineering, 2002, 23(6): 12-15.(in Chinese)[5]付强,袁寿其,朱荣生,等. 1 000 MW核电站SEC系统鼓型滤网抗震计算[J]. 核动力工程,2010,31(6):10-14. Fu Qiang, Yuan Shouqi, Zhu Rongsheng, et al. Anti-seismic calculation of the drum filter in SEC system for 1 000 MW nuclear power plants[J]. Nuclear Power Engineering, 2010, 31(6): 10-14.(in Chinese)[6]刘厚林,徐欢,王凯,等. 基于流固耦合的余热排出泵转子模态分析[J]. 流体机械,2012,40(6):28-32. Liu Houlin, Xu Huan, Wang Kai, et al. Modal analysis for rotor of residual heat removal pump based on fluid-structure interaction[J]. Fluid Machinery, 2012, 40(6): 28-32.(in Chinese)[7]付强,袁寿其,朱荣生,等. 1 000 MW级核电站离心式上充泵转子轴系的扭矩特性[J]. 排灌机械工程学报,2013,31(5):394-400. Fu Qiang, Yuan Shouqi, Zhu Rongsheng, et al. Torsional vibration characteristics of rotor for 1 000 MW centrifugal charging pump[J]. Journal of Drainage and Irrigation Machinery Engineering, 2013, 31(5): 394-400.(in Chinese)[8]刘松. 核泵主轴机械-热耦合疲劳问题研究[D]. 大连:大连理工大学船舶工程学院,2012.[9]付强. 1 000 MW核电站离心式上充泵水力设计与结构可靠性研究[D]. 镇江:江苏大学国家水泵及系统工程技术研究中心,2010.[10]杨世铭,陶文铨. 传热学[M]. 北京:高等教育出版社,2006.[11]American Society of Mechanical Engineers. Boiler and Pressure Vessel Code,Section Ⅱ:Materials: Part D[S]. New York:ASME,2013.[12]American Society of Mechanical Engineers. Boiler and Pressure Vessel Code,Section Ⅲ:Rules for Construction of Nuclear Power Plant Components[S]. New York:ASME,2004. |
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