1000MW核电站双壳体离心式上充泵抗震计算
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摘要
采用有限元Ansys软件建立离心式上充泵三维模型和划分有限元网格,对其结构进行固有模态分析,并采用静力法按SSE地震载荷计算上充泵的抗震性能,并将自重、温度、工作压力等载荷的作用结果与地震载荷的作用结果按SRSS组合.结果表明:离心式上充泵结构的基频为655.13Hz,远大于33Hz,为刚性结构;上充泵最大Von Mises等效应力发生在外壳体中部,为103.40MPa,小于ASME-Ⅱ所确定的该材料许用应力140.23MPa;位移最大响应发生在外壳体中部,为0.143mm,远小于各部件最小1mm间隙,满足抗震规范要求.
An inherent modal analysis has been performed on the structure of a centrifugal charging pump with Ansys software based on a newly developed 3D model.Using static method,its anti-seismic performance at SSE seismic load has been analyzed according to SRSS algorithm by simultaneously considering the actions of the gravity,temperature and pressure load.Results show that the fundamental frequency of the charging pump body is 655.13 Hz,far more than 33 Hz,indicating that the structure is rigid;the biggest Mises equivalent stress is 103.40 MPa,appearing in the middle area of outer casing,less than the material allowable stress 140.23 MPa specified by ASME-Ⅱ;the maximum displacement response is 0.143 mm,occurring in the middle area of outer casing,far below the gap of 1mm left between various components.Calculation results prove the charging pump to be satisfactory according to relevant standards.
An inherent modal analysis has been performed on the structure of a centrifugal charging pump with Ansys software based on a newly developed 3D model.Using static method,its anti-seismic performance at SSE seismic load has been analyzed according to SRSS algorithm by simultaneously considering the actions of the gravity,temperature and pressure load.Results show that the fundamental frequency of the charging pump body is 655.13 Hz,far more than 33 Hz,indicating that the structure is rigid;the biggest Mises equivalent stress is 103.40 MPa,appearing in the middle area of outer casing,less than the material allowable stress 140.23 MPa specified by ASME-Ⅱ;the maximum displacement response is 0.143 mm,occurring in the middle area of outer casing,far below the gap of 1mm left between various components.Calculation results prove the charging pump to be satisfactory according to relevant standards.
引文
[1]TOSHIHIKO Hirama,MASASHI Goto,HITOSHIKumagai.Seismic proof test of a reinforced concretecontainment vessel(RCCV)part 3:evaluation ofseismic safety margin[J].Nuclear Engineering andDesign,2007,237(11):1128-1139.
[2]ZHANG Zhengming,HE Shuyan,XU Ming.Seis-mic analysis of liquid storage container in nuclear re-actors[J].Nuclear Engineering and Design,2007,237(12/13):1325-1331.
[3]李水安.西安脉冲堆抗震设计计算[J].核动力工程,2002,23(6):12-15.LI Shuian.Calculation of anti-seismic design for Xi’an pulsed reactor[J].Nuclear Power Engineering,2002,23(6):12-15.
[4]孙柏涛,刘殿魁,丰彪.巴基斯坦恰希玛核电站P300工程核级冷冻机组抗震力学性能计算分析[J].地震工程与工程振动,2000,20(2):61-67.SUN Baitao,LIU Diankui,FENG Biao.Seismic a-nalysis for freezing unti of P300project of Charshimanuclear power station in Pakistan[J].Earthquake En-gineering and Engineering Vibration,2000,20(2):61-67.
[5]KOSTAREV V V,ETRENKO A V,VASILYEV PS.An advanced seismic analysis of an NPP powerfulturbogenerator on an isolation pedestal[J].NuclearEngineering and Design,2007,237(12/13):1315-1324.
[6]盛选禹,雒晓卫,傅激扬.反应堆主泵抗震强度的三维实体模型计算[J].核动力工程,2005,26(5):471-474.SHENG Xuanyu,LUO Xiaowei,FU Jiyang.Aseis-matic strength analysis of main nuclear reactor pumpbased on real three dimension model[J].NuclearPower Engineering,2005,26(5):471-474.
[7]杨晓丰,张勇,孙柏涛,等.核电站用屏蔽泵的抗震力学性能计算分析[J].世界地震工程,2007,23(3):47-53.YANG Xiaofeng,ZHANG Yong,SUN Baitao,etal.Seismic analysis on canned motor pump used innuclear power generating station[J].World Earth-quake Engineering,2007,23(3):47-53.
[8]周文建,陈宏,闻邦椿.核电站反应堆冷却剂泵的地震响应分析[J].振动与冲击,2006,25(1):32-35.ZHOU Wenjian,CHEN Hong,WEN Bangchun.Seismic response analysis of reactor coolant pump innuclear power plant[J].Journal of Vibration andShock,2006,25(1):32-35.
[9]邓德兵,赵清森,陈伟,等.核电站汽轮机运行性能监测与诊断[J].动力工程学报,2011,31(8):585-589.DENG Debing,ZHAO Qingsen,CHEN Wei,et al.Performance monitoring and fault diagnosis of wet-steam turbines for nuclear power plants[J].Journalof Chinese Society of Power Engineering,2011,31(8):585-589.
[10]谷俊杰,米克嵩,徐培培.基于遗传算法的核电站蒸发器高阶水位模型的降阶方法[J].动力工程学报,2010,30(2):115-117.GU Junjie,MI Kesong,XU Peipei.Order reductionmethod of the high order nuclear steam generator lev-el control model based on genetic algorithm[J].Jour-nal of Chinese Society of Power Engineering,2010,30(2):115-117.
[11]袁寿其,付强,朱荣生.核电站离心式上充泵多工况水力设计[J].排灌机械工程学报,2010,28(3):185-189.YUAN Shouqi,FU Qiang,ZHU Rongsheng.Multi-operating-condition hydraulic design of centrifugalcharging pump for nuclear power plant[J].Journal ofDrainage and Irrigation Machinery Engineering,2010,28(3):185-189.
[12]孔繁余,王婷,黄道见,等.核电站余热排出泵热冲击回路设计[J].排灌机械工程学报,2010,28(4):291-294.KONG Fanyu,WANG Ting,HUANG Daojian,etal.Design for thermal shock loop of residual heat re-moval pump in nuclear power plant[J].Journal ofDrainage and Irrigation Machinery Engineering,2010,28(4):291-294.
[13]许德忠,孔令杰,林冲.CPR1000MW核电站上充泵介绍[J].水泵技术,2007(6):9-14.XU Dezhong,KONG Lingjie,LIN Chong.Introduceof CPR 1 000 MW nuclear power plants chargingpump[J].Pump Technology,2007(6):9-14.
[14]United States Nuclear Regulatory Commission.NRCRG 1.61damping values for seismic design of nuclearpower plants[S].New York:[s.n.],2007.
[15]国家地震局.GB50267—1997核电厂抗震设计规范[S].北京:中国计划出版社,1998.
[16]American Society of Mechanical Engineers.Boilerand pressure vessel code,sectionⅢ:rules for con-struction of nuclear power plant components,division1,subsection nc:class 2 components[S].NewYork:ASME,2004.
[2]ZHANG Zhengming,HE Shuyan,XU Ming.Seis-mic analysis of liquid storage container in nuclear re-actors[J].Nuclear Engineering and Design,2007,237(12/13):1325-1331.
[3]李水安.西安脉冲堆抗震设计计算[J].核动力工程,2002,23(6):12-15.LI Shuian.Calculation of anti-seismic design for Xi’an pulsed reactor[J].Nuclear Power Engineering,2002,23(6):12-15.
[4]孙柏涛,刘殿魁,丰彪.巴基斯坦恰希玛核电站P300工程核级冷冻机组抗震力学性能计算分析[J].地震工程与工程振动,2000,20(2):61-67.SUN Baitao,LIU Diankui,FENG Biao.Seismic a-nalysis for freezing unti of P300project of Charshimanuclear power station in Pakistan[J].Earthquake En-gineering and Engineering Vibration,2000,20(2):61-67.
[5]KOSTAREV V V,ETRENKO A V,VASILYEV PS.An advanced seismic analysis of an NPP powerfulturbogenerator on an isolation pedestal[J].NuclearEngineering and Design,2007,237(12/13):1315-1324.
[6]盛选禹,雒晓卫,傅激扬.反应堆主泵抗震强度的三维实体模型计算[J].核动力工程,2005,26(5):471-474.SHENG Xuanyu,LUO Xiaowei,FU Jiyang.Aseis-matic strength analysis of main nuclear reactor pumpbased on real three dimension model[J].NuclearPower Engineering,2005,26(5):471-474.
[7]杨晓丰,张勇,孙柏涛,等.核电站用屏蔽泵的抗震力学性能计算分析[J].世界地震工程,2007,23(3):47-53.YANG Xiaofeng,ZHANG Yong,SUN Baitao,etal.Seismic analysis on canned motor pump used innuclear power generating station[J].World Earth-quake Engineering,2007,23(3):47-53.
[8]周文建,陈宏,闻邦椿.核电站反应堆冷却剂泵的地震响应分析[J].振动与冲击,2006,25(1):32-35.ZHOU Wenjian,CHEN Hong,WEN Bangchun.Seismic response analysis of reactor coolant pump innuclear power plant[J].Journal of Vibration andShock,2006,25(1):32-35.
[9]邓德兵,赵清森,陈伟,等.核电站汽轮机运行性能监测与诊断[J].动力工程学报,2011,31(8):585-589.DENG Debing,ZHAO Qingsen,CHEN Wei,et al.Performance monitoring and fault diagnosis of wet-steam turbines for nuclear power plants[J].Journalof Chinese Society of Power Engineering,2011,31(8):585-589.
[10]谷俊杰,米克嵩,徐培培.基于遗传算法的核电站蒸发器高阶水位模型的降阶方法[J].动力工程学报,2010,30(2):115-117.GU Junjie,MI Kesong,XU Peipei.Order reductionmethod of the high order nuclear steam generator lev-el control model based on genetic algorithm[J].Jour-nal of Chinese Society of Power Engineering,2010,30(2):115-117.
[11]袁寿其,付强,朱荣生.核电站离心式上充泵多工况水力设计[J].排灌机械工程学报,2010,28(3):185-189.YUAN Shouqi,FU Qiang,ZHU Rongsheng.Multi-operating-condition hydraulic design of centrifugalcharging pump for nuclear power plant[J].Journal ofDrainage and Irrigation Machinery Engineering,2010,28(3):185-189.
[12]孔繁余,王婷,黄道见,等.核电站余热排出泵热冲击回路设计[J].排灌机械工程学报,2010,28(4):291-294.KONG Fanyu,WANG Ting,HUANG Daojian,etal.Design for thermal shock loop of residual heat re-moval pump in nuclear power plant[J].Journal ofDrainage and Irrigation Machinery Engineering,2010,28(4):291-294.
[13]许德忠,孔令杰,林冲.CPR1000MW核电站上充泵介绍[J].水泵技术,2007(6):9-14.XU Dezhong,KONG Lingjie,LIN Chong.Introduceof CPR 1 000 MW nuclear power plants chargingpump[J].Pump Technology,2007(6):9-14.
[14]United States Nuclear Regulatory Commission.NRCRG 1.61damping values for seismic design of nuclearpower plants[S].New York:[s.n.],2007.
[15]国家地震局.GB50267—1997核电厂抗震设计规范[S].北京:中国计划出版社,1998.
[16]American Society of Mechanical Engineers.Boilerand pressure vessel code,sectionⅢ:rules for con-struction of nuclear power plant components,division1,subsection nc:class 2 components[S].NewYork:ASME,2004.
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