核级主给水控制阀性能评估技术研究
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摘要
针对核二级主给水控制阀抗震性能评估的要求,基于ASME规范和Femap+NX Nastran有限元平台,研究核阀虚拟性能评估技术。首先,针对直立式控制阀门的结构特点,提出了直立式控制阀执行机构力学模型,给出了结构风险评估及改进方法。然后,对于某型号控制阀进行仿真分析,通过实验数据和仿真数据的对比,验证了有限元分析技术的有效性;最后,对所设计的核二级主给水控制阀在地震载荷及设计组合载荷作用下的抗震性能进行分析。典型部位处的应力仿真结果与经验公式计算结果误差小于5%。仿真结果表明所设计阀门整体自振频率大于33 Hz,具有良好的抗震性能,并且各工况下阀门承受应力在许用应力范围内,满足设计要求。
A performance evaluation technology was studied for the seismic performance evaluation of nuclear safety Class II main feed-water control valve based on the ASME Code and finite element analysis platform( Femap + NX Nastran).First,we proposed an analysis model for the vertical control valve,and the risk assessment and improvement methods for the structural characteristics of vertical control valve were studied.Then we conducted a numerical model for a control valve and compared the simulation data with those obtained from experimental test.These two showed good agreement.Finally,the seismic performance evaluation of a main feed-water control valve was performed under the combination of the seismic load and design load.The simulated relative error of inner stresses at typical site is less than 5% compared with that obtained by using empirical formula.The simulated data shows that the designed valve fulfills the design requirement for its first order frequency is bigger than 33 HZ,and the maximum stresses are within the allowable range under various load cases.
A performance evaluation technology was studied for the seismic performance evaluation of nuclear safety Class II main feed-water control valve based on the ASME Code and finite element analysis platform( Femap + NX Nastran).First,we proposed an analysis model for the vertical control valve,and the risk assessment and improvement methods for the structural characteristics of vertical control valve were studied.Then we conducted a numerical model for a control valve and compared the simulation data with those obtained from experimental test.These two showed good agreement.Finally,the seismic performance evaluation of a main feed-water control valve was performed under the combination of the seismic load and design load.The simulated relative error of inner stresses at typical site is less than 5% compared with that obtained by using empirical formula.The simulated data shows that the designed valve fulfills the design requirement for its first order frequency is bigger than 33 HZ,and the maximum stresses are within the allowable range under various load cases.
引文
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[2]李军业,张宗列.核电阀门设计规范的探讨[J].阀门,2009(06):32-37.LI Jun Ye,ZHANG Zong Lie.Discussion of nuclear valves design specification[J].Valve,2009(06):32-37(In Chinese).
[3]秦武,李志鹏,靳卫华.核阀的使用现状和发展[J].通用机械,2008(01):41-46.QIN Wu,LI Zhi Peng,JIN Wei Hua.Nuclear valve's using status and development direction[J].General Machinery,2008(01):41-46(In Chinese).
[4]刘金梁,王忠诚.核级阀门抗震分析与研究[J].阀门,2011(2):34-37.LIU Jin Liang,WANG Zhong Cheng.Study on anti-earthquake analysis of nuclear valve[J].Valve,2011(2):34-37(In Chinese).
[5]Di Jiejian.Modeling and Nonlinear Seismic Analysis of Thyristor Valves[J].PEITS 2010:20-26.
[6]吕振华,伍卓安.减振器节流阀非线性特性的有限元模拟分析[J].机械强度,2003,25(6):614-620.LV Zhen Hua,WU Zhuo An.Finite elements simulation of nonlinear dynamic characteristics of hydraulic damper’s valve[J].Journal of Mechanical Strength,2003,25(6):614-620(In Chinese).
[7]张燕星,邓芝娟.高温条件下钢结构的应力-温度-应变的关系[J].建设科技,2005(8):76-79.ZHANG Yan Xing,DENG Zhi Juan.Stress-temperature-strain relationship of steel structure at high temperatures[J].Construction Science and Technology,2005(8):76-79(In Chinese).
[8]陈天敏.核二级电动闸阀抗震分析[J].通用机械,2011(10):55-58.CHEN Tian Min.Seismic analysis of nuclear safety Class II electric valve[J].General Machinery,2011(10):55-58(In Chinese).
[9]俞树荣,梁瑞.压力容器设计制造入门与精通[M].北京:机械工业出版社,2013:174-175.YU Shu Yong,LIANG Rui.Entry and proficiency of design and manufacture for pressure vessels[M].Beijing:China Machine Press,2013:174-175(In Chinese).