Fracture Analysis and Working Stress Calculation of Bearing Cage Used in Charging Pump in a Nuclear Power Plant

被引:2
|
作者
Chen, Qiang [1 ,2 ,3 ,4 ]
Jiang, Shengli [3 ,4 ]
Duan, Deli [3 ,4 ]
机构
[1] Suzhou Nucl Power Res Inst Co Ltd, Shenzhen 518000, Peoples R China
[2] Natl Engn Res Ctr Nucl Power Plant Safety & Reliab, Sch Mat Sci & Engn, Shenzhen 518000, Peoples R China
[3] Univ Sci & Technol China, Sch Mat Sci & Engn, Shenyang 110016, Peoples R China
[4] Chinese Acad Sci, Shi Changxu Innovat Ctr Adv Mat, Inst Met Res, Shenyang 110016, Peoples R China
关键词
bearing; cage; fatigue fracture; finite element calculation; nuclear power plant; BALL-BEARING; RESIDUAL-STRESSES; FATIGUE FAILURE; TOUGHNESS; BEHAVIOR;
D O I
10.3390/met13081380
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
This paper presents an analysis of the fracture accident of a cylindrical roller bearing cage used in a charging pump in a nuclear power plant. The causes and mechanisms of bearing cage breakage were investigated by material failure analysis and simulation calculations. Macroscopic observation results confirmed that the cage fracture occurred at the stress concentration position. The microfracture morphology of the cage obtained from scanning electron microscopy showed a fatigue feature. The analysis of residual stress indicated large residual stress perpendicular to the fracture surface. The finite element calculation showed that when the bearing was moving in and out of the working area during operation, large working stress appeared at the stress concentration position. Working stress and residual stress acted together, approaching the fatigue limit of materials, and finally led to the cage fatigue fracture. The stress of the other two structural cages of the same type of bearing was also calculated, and no such large stress concentration was identified; thus, one plastic cage was temporarily used.
引用
收藏
页数:14
相关论文
共 15 条
  • [1] Analysis on Wearing of Bearing for Main Pump in Nuclear Power Plant
    Zhang H.
    Huang Z.
    Jiao S.
    Dai H.
    Xu X.
    Sheng F.
    Hedongli Gongcheng/Nuclear Power Engineering, 2022, 43 (02): : 108 - 111
  • [2] Failure analysis on premature fracture of anchor bolts in seawater booster pump of nuclear power plant
    Gong, Yi
    Ding, Qun
    Yang, Zhen-Guo
    ENGINEERING FAILURE ANALYSIS, 2019, 97 : 10 - 19
  • [3] SEISMIC ANALYSIS OF NUCLEAR POWER PLANT CANNED MOTOR PUMP UNIT BASED ON INTEGRAL CALCULATION METHOD
    Li Zhenggui
    Li Muyu
    Zhang Jiarong
    Li Bo
    Liu Xiaobing
    Yang Fengyu
    CIVIL ENGINEERING JOURNAL-STAVEBNI OBZOR, 2016, 25 (04):
  • [4] Failure analysis on the O-ring of radial thrust bearing room of main pump in a nuclear power plant
    Mo, Yi-Min
    Gong, Yi
    Yang, Zhen-Guo
    ENGINEERING FAILURE ANALYSIS, 2020, 115
  • [5] Failure analysis on premature fracture of boric acid recycle pump shaft in 1000 MW nuclear power plant
    Ni, Tong-Wei
    Ding, Qun
    Yang, Zhen-Guo
    Zheng, Hong-Lian
    Lou, Xiao
    ENGINEERING FAILURE ANALYSIS, 2018, 92 : 317 - 326
  • [6] Seismic analysis for axial fan used in nuclear power plant
    Xu, Wenbing
    Xiang, Wenyuan
    Lv, Yonghong
    Lu, Guangyao
    APPLIED MECHANICS, MATERIALS AND MANUFACTURING IV, 2014, 670-671 : 1134 - 1139
  • [7] Stress and fracture analyses of nuclear power plant LP turbine rotor discs
    Lee, CY
    Kwon, JD
    Chai, YS
    Jang, KS
    KSME INTERNATIONAL JOURNAL, 2000, 14 (02): : 207 - 214
  • [8] Stress and fracture analyses of nuclear power plant LP turbine rotor discs
    Choon-Yeol Lee
    Jae-Do Kwon
    Young S. Chai
    Ki-Sang Jang
    KSME International Journal, 2000, 14 : 207 - 214
  • [9] Test Method on Starting Drag Torque of the Thrust Bearing of the Reactor Main Pump in Nuclear Power Plant
    Zhang J.
    Gu J.
    Chen S.
    Wang M.
    Liu X.
    Hedongli Gongcheng/Nuclear Power Engineering, 2022, 43 (02): : 232 - 236
  • [10] Transient flow characteristics during variable operating conditions of the centrifugal charging pump in 1000 MW nuclear power plant
    Zhang, Fan
    Yuan, Shouqi
    Fu, Qiang
    Pei, Ji
    Chen, JingJun
    PROCEEDINGS OF THE INSTITUTION OF MECHANICAL ENGINEERS PART E-JOURNAL OF PROCESS MECHANICAL ENGINEERING, 2015, 229 (04) : 233 - 242