空间核动力装置控制鼓系统试验样机热态性能试验
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摘要
控制鼓系统是空间核动力装置上执行功率调节、紧急停堆的重要安全设备,其能否正常运行直接关系到核动力装置的安全性。为验证控制鼓系统能否满足设计要求,必须进行热态下的性能试验。本文采用1∶1全尺寸控制鼓系统试验样机,通过设计建立专用的热态性能试验装置,对试验样机寿期内全行程往复、电机切换和快速复位功能进行了试验验证和研究分析。试验过程显示,试验样机运行基本平稳,无异响和卡顿,快速复位时间满足设计指标,但传动链终端存在角度滞后、旋转过程位置重复精度低和小角度快速复位乏力等现象。该控制鼓系统试验样机机构设计基本满足机械运转功能,为下一阶段控制鼓系统结构的优化与定型奠定了基础。
The control drum system is important for power regulation and emergency shutdown of the space nuclear power plant. The safety of the reactor directly depends on whether the control drum system can operate well or not. In order to check whether the control drum system can meet the design requirements, it is necessary to carry out the performance test of the system under high temperature. The full-scale model of the control drum system was selected as the target of the hot performance test. The specific hot performance test facility was designed and installed. On the basis of the facility, series of testing, research and analysis were carried out, such as whole route reciprocating motion testing, motor switch testing and scram testing, etc. The results show that the full-scale model of the control drum system operates normally and has no abnormal sound and stuck or stagnation, and scram time meets the design target. However, there are some phenomena such as angle stagnation, low position accuracy during the restoration and lacking strength during small angle scram in the termination of the transmission chain. The mechanical design of the control drum system basically meets the functional requirements, which lays the foundation of the optimization and finalization of the control drum system in the next stage.
The control drum system is important for power regulation and emergency shutdown of the space nuclear power plant. The safety of the reactor directly depends on whether the control drum system can operate well or not. In order to check whether the control drum system can meet the design requirements, it is necessary to carry out the performance test of the system under high temperature. The full-scale model of the control drum system was selected as the target of the hot performance test. The specific hot performance test facility was designed and installed. On the basis of the facility, series of testing, research and analysis were carried out, such as whole route reciprocating motion testing, motor switch testing and scram testing, etc. The results show that the full-scale model of the control drum system operates normally and has no abnormal sound and stuck or stagnation, and scram time meets the design target. However, there are some phenomena such as angle stagnation, low position accuracy during the restoration and lacking strength during small angle scram in the termination of the transmission chain. The mechanical design of the control drum system basically meets the functional requirements, which lays the foundation of the optimization and finalization of the control drum system in the next stage.
引文
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[10] 王平易.无间隙齿轮传动装置的设计与应用[J].机械研究与应用,2014,27(6):173-174.WANG Pingyi.Design and application of gapless gear driving device[J].Mechanical Research and Application,2014,27(6):173-174(in Chinese).
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[12] 王丰,沈秋平.控制棒驱动机构老化机理及影响分析[J].机械工程师,2014(5):187-188.WANG Feng,SHEN Qiuping.Aging mechanism and effect analysis of control rod drive mechanism[J].Mechanical Engineer,2014(5):187-188(in Chinese).
[13] 杨平汉.压水堆控制棒驱动机构失效模式和影响分析[J].上海电气技术,2014,7(2):52-57.YANG Pinghan.The common failure mode and effects analysis of the pressurized water reactor control rod drive mechanism[J].Journal of Shanghai Electric Technology,2014,7(2):52-57(in Chinese).
[14] 于耀华,李翔,吴伟建.控制棒驱动机构出厂性能试验研究[J].装备机械,2017(1):52-56.YU Yaohua,LI Xiang,WU Weijian.The factory performance test research of control rod drive mechanism[J].Equipment Machinery,2017(1):52-56(in Chinese).
[2] 胡古,赵守智.空间核反应堆电源技术概览[J].深空探测学报,2017,4(5):430-443.HU Gu,ZHAO Shouzhi.Overview of space nuclear reactor power technology[J].Journal of Deep Space Exploration,2017,4(5):430-443(in Chinese).
[3] GJB 5405—2005.空间热离子反应堆核动力装置术语[S].北京:国防科学技术工业委员会,2005.
[4] 杨平汉.压水堆控制棒驱动机构结构设计与制造[J].装备机械,2014(2):20-26.YANG Pinghan.The structural design and manufacture of the PWR control rod drive mechanism[J].Equipment Machinery,2014(2):20-26(in Chinese).
[5] 王英,郎爱国,顾申杰,等.核安全设备鉴定[M].北京:机械工业出版社,2016.
[6] 闰贺,杨磊,张作鹏,等.高温气冷堆控制棒驱动机构冷态落棒试验研究[J].核科学与工程,2015,35(3):479-485.YAN He,YANG Lei,ZHANG Zuopeng,et al.Dropping time measurement of the HTR control rod prototype[J].Nuclear Science and Engineering,2015,35(3):479-485(in Chinese).
[7] 郑海峰,钟艳敏,王源,等.先进堆长寿命控制棒驱动机构热态寿命考验[J].核动力工程,2002,23(2):70-73.ZHENG Haifeng,ZHONG Yanmin,WANG Yuan,et al.Longeval control rod drive mechanism hot life test for advance pressurized water reactor[J].Nuclear Power Engineering,2002,23(2):70-73(in Chinese).
[8] 冷承木,董银华.铀氮错反应堆稳态控制棒驱动机构的设计和试验[J].核动力工程,1984,5(5):80-83.LENG Chengmu,DONG Yinhua.The design and test of a steady-state CRDM for UHZr reactor[J].Nuclear Power Engineering,1984,5(5):80-83(in Chinese).
[9] JB/T 7366—1994.平面涡卷弹簧设计计算[S].北京:机械工业部,1994.
[10] 王平易.无间隙齿轮传动装置的设计与应用[J].机械研究与应用,2014,27(6):173-174.WANG Pingyi.Design and application of gapless gear driving device[J].Mechanical Research and Application,2014,27(6):173-174(in Chinese).
[11] 伍利群.齿轮传动间隙的消除方法[J].机床与液压,2005(5):187-188.WU Liqun.The elimination ways of the gear-driven clearance[J].Machine Tool and Hydraulics,2005(5):187-188(in Chinese).
[12] 王丰,沈秋平.控制棒驱动机构老化机理及影响分析[J].机械工程师,2014(5):187-188.WANG Feng,SHEN Qiuping.Aging mechanism and effect analysis of control rod drive mechanism[J].Mechanical Engineer,2014(5):187-188(in Chinese).
[13] 杨平汉.压水堆控制棒驱动机构失效模式和影响分析[J].上海电气技术,2014,7(2):52-57.YANG Pinghan.The common failure mode and effects analysis of the pressurized water reactor control rod drive mechanism[J].Journal of Shanghai Electric Technology,2014,7(2):52-57(in Chinese).
[14] 于耀华,李翔,吴伟建.控制棒驱动机构出厂性能试验研究[J].装备机械,2017(1):52-56.YU Yaohua,LI Xiang,WU Weijian.The factory performance test research of control rod drive mechanism[J].Equipment Machinery,2017(1):52-56(in Chinese).