核主泵水润滑推力轴承试验的磨损颗粒研究
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摘要
某核主泵水润滑推力轴承在试验浸银石墨瓦时,在类似热瞬态工况时出现异常振动及噪声,拆机发现石墨推力瓦和推力盘硬化层表面均出现较严重磨损,且石墨推力瓦出现局部剥落。采用化学、光学、X射线衍射、扫描电镜、透射电镜、电子探针等方法研究水润滑轴承试验的磨损颗粒相结构、形貌、成分、组织和磨损表面特征;明确热瞬态时不锈钢推力盘硬化层与石墨推力瓦的摩擦磨损形式和过程,得出水润滑推力轴承已经进入边界润滑状态,局部发生干摩擦的结论;提出一些改进建议,如将水润滑轴承瓦面材料改为碳素纤维复合材料以增加抗磨性能,改善瓦面形状以减少热变形,增加接触曲面硬化层以控制高应力曲面接触的微动磨损。
When testing the silver impregnated graphite pad of the water-lubricated thrust bearing for a nuclear main pump,unusual vibration and noise occur at transient thermal like working conditions,and serious wear are observed on the surfaces of both graphite pad and thrust plate after the thrust bearing disassembling,and even some partial peeling occur on local region on graphite pad surface. The wear debris was analyzed by using a number of techniques including chemical,optical,XRD,SEM-EDS,TEM,and EPMA to study their phase structure,morphology,composition and microstructure as well as worn surface features,respectively. The wear behavior and process of the graphite pad and Stellite hard-faced thrust plate in thermal transient were identified,and the conclusion was drawn that the water-lubricated thrust bearing is in a condition of boundary lubrication state,and local dry friction was taken place. It is suggested that,using carbon fiber composite instead of silver impregnated graphite to improve the wear performance of thrust bearing,optimizing the surface configuration of pad to reduce thermal deformation during friction,and increasing surface hardening layer on the supporting contact faces to control the fretting wear due to the high stress contact among the bearing components.
When testing the silver impregnated graphite pad of the water-lubricated thrust bearing for a nuclear main pump,unusual vibration and noise occur at transient thermal like working conditions,and serious wear are observed on the surfaces of both graphite pad and thrust plate after the thrust bearing disassembling,and even some partial peeling occur on local region on graphite pad surface. The wear debris was analyzed by using a number of techniques including chemical,optical,XRD,SEM-EDS,TEM,and EPMA to study their phase structure,morphology,composition and microstructure as well as worn surface features,respectively. The wear behavior and process of the graphite pad and Stellite hard-faced thrust plate in thermal transient were identified,and the conclusion was drawn that the water-lubricated thrust bearing is in a condition of boundary lubrication state,and local dry friction was taken place. It is suggested that,using carbon fiber composite instead of silver impregnated graphite to improve the wear performance of thrust bearing,optimizing the surface configuration of pad to reduce thermal deformation during friction,and increasing surface hardening layer on the supporting contact faces to control the fretting wear due to the high stress contact among the bearing components.
引文
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[4]李建国,吴军令,梁广泰.09-Ⅲ主泵屏蔽电机推力轴承润滑性能研究[J].大电机技术,1997(1):21-26.LI J G,WU J L,LIANG G T.Study on the lubrication performance of a thrust bearing for a main-pump motor[J].Large Electric Machine and Hydraulic Turbine,1997(1):21-26.
[5]武中德,张宏,于秋敏,等.屏蔽电机水润滑推力轴承润滑性能研究[J].大电机技术,2003(7):56-57.WU Z D,ZHANG H,YU Q M,et al.Investigation on lubrication performance of water-lubrication trust bearing for the shielding motor[J].Large Electric Machine and Hydraulic Turbine,2003(7):56-57.
[6]陈为平,高诚辉,任志英,等.抛光过程游离单颗磨粒与光学元件间滚动摩擦接触分析[J].图学学报,2015,36(4):537-545.CHEN W P,GAO C H,REN Z Y,et al.Analysis of rolling friction contact between free single abrasive and optical element[J].Paper Science&Technology,2015,36(4):537-545.
[7]核电主泵电机技术条件.第2部分:屏蔽泵异步电机:NB/T42032.2[S].
[8]郎明刚,高祖瑛,周志伟,等.大亚湾核电厂全场“断电”事故裂变产物行为计算[J].核科学与工程,2002,22(4):339-342.LANG M G,GAO Z Y,ZHOU Z W,et al.Calculation of fission product behaviour in a station blackout accident of Daya bay nuclear power plant[J].Chinese Journal of Nuclear Science And Engineering,2002,22(4):339-342.
[9]阮良成,薛长江,商幼明.秦山第二核电厂一回路主系统水压试验实践经验[J].核科学与工程,2006,26(3):249-256.RUAN L C,XUE C J,SHANG Y M.Practical experience of the main primary system hydraulic tests for Qinshan NPP PhaseⅡ[J].Chinese Journal of Nuclear Science and Engineering,2006,26(3):249-256.
[10]唐琼辉,周瑞,吴应喜,等.失水事故下一回路动力载荷分析[J].核科学与工程,2014,34(4):462-468.TANG Q H,ZHOU R,WU Y X,et al.Analysis of hydrodynamic force of the primary loop under LOCA condition[J].Nuclear Science and Engineering,2014,34(4):462-468.
[11]王华杰.冲击动载荷系数的一般形式[J].力学与实践,1997(3):57-59.