核主泵水润滑推力轴承不锈钢螺纹锁死分析及改进
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摘要
本文通过对某核主泵推力轴承不锈钢螺纹锁死现象进行分析,还原了发生的具体过程,分析了螺纹损伤原因。提出了一种拆解此类轴承螺纹副锁死的方法,优化了相关部件结构及装配工艺。在推力轴承装配间隙不合格无法拆解时,降低了核主泵产品因螺纹锁死带来的损失。
In this paper,a thrust bearing stainless steel threaded locking phenomenon is analyzed,and the specific occurring process is restored,and the reasons for the thread damage are analyzed.A method is presented for the disassembly of the screw thread pair of this kind of bearing,which optimizes the structure of relevant parts and assembly process.When the thrust bearing can't be dismantled due to unqualified assembly clearance,the loss of nuclear primary pump products is reduced caused by the thread lock.
In this paper,a thrust bearing stainless steel threaded locking phenomenon is analyzed,and the specific occurring process is restored,and the reasons for the thread damage are analyzed.A method is presented for the disassembly of the screw thread pair of this kind of bearing,which optimizes the structure of relevant parts and assembly process.When the thrust bearing can't be dismantled due to unqualified assembly clearance,the loss of nuclear primary pump products is reduced caused by the thread lock.
引文
[1]Dr.Sven Baumgarten,Bernhard Brecht,Uwe Bruhns.Reactor Coolant Pump Type RUV for Westinghouse Reactor AP1000[C].Proceedings of ICAPP'10,2010June 13-17,Paper 10339.
[2]W.E.Cummins,M.M.Corletti,T.L.Schulz.Westinghouse AP1000 Advanced Passive Plant[C].Proceedings of ICAPP'03,2003 May 4-7,Paper 3235.
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[5]糖琼辉,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(4):462468,474.TANG Qiong-hui,ZHOU Rui,WU Ying-xi,et al.Analysis of Hydrodynamic Force of the Primary Loop under LOCA Condition[J].Chinese Journal of Nuclear Science and Engineering.2014(4):462-468,474.
[6]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.WANG Hua-jie.General Form of Impact Dynamic Load Coefficient[J].Mechanics in Engineering,1997(3):57-59.
[7]李梦启.王伟光,李臧雪,等.核主泵水润滑推力轴承试验的磨损颗粒研究[J].润滑与密封,2016(9):113-120.LI Meng-qi,WANG Wei-guang,LI Cang-xue,et al.Study on Wear Debris in Water Lubricated Thrust Bearing of Nuclear Primary Pump after Rig Test[J].Lubrication Engineering,2016(9):113-120.
[2]W.E.Cummins,M.M.Corletti,T.L.Schulz.Westinghouse AP1000 Advanced Passive Plant[C].Proceedings of ICAPP'03,2003 May 4-7,Paper 3235.
[3]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(4):339-342.LANG Ming-gang,GAO Zu-ying,ZHOU Zhi-wei,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(4):339-342.
[4]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(3):249-256.RUAN Liang-cheng,XUE Chang-jiang,SHANG You-ming.Practical Experience of the Primary System Hydraulic Tests for Qinshan NPP PhaseⅡ[J].Chinese Journal of Nuclear Science and Engineering,2006(3):249-256.
[5]糖琼辉,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(4):462468,474.TANG Qiong-hui,ZHOU Rui,WU Ying-xi,et al.Analysis of Hydrodynamic Force of the Primary Loop under LOCA Condition[J].Chinese Journal of Nuclear Science and Engineering.2014(4):462-468,474.
[6]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.WANG Hua-jie.General Form of Impact Dynamic Load Coefficient[J].Mechanics in Engineering,1997(3):57-59.
[7]李梦启.王伟光,李臧雪,等.核主泵水润滑推力轴承试验的磨损颗粒研究[J].润滑与密封,2016(9):113-120.LI Meng-qi,WANG Wei-guang,LI Cang-xue,et al.Study on Wear Debris in Water Lubricated Thrust Bearing of Nuclear Primary Pump after Rig Test[J].Lubrication Engineering,2016(9):113-120.