PERFORMANCE EVALUATION TECHNIQUES FOR THE NUCLEAR GRADE MAIN FEED-WATER CONTROL VALVE

LIU QingMin; GAO ZhaoJie; LIN Feng; ZHANG QiangSheng; WU Xin

doi:10.16579/j.issn.1001.9669.2015.05.023

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PERFORMANCE EVALUATION TECHNIQUES FOR THE NUCLEAR GRADE MAIN FEED-WATER CONTROL VALVE

更新时间：2022-09-22

- PERFORMANCE EVALUATION TECHNIQUES FOR THE NUCLEAR GRADE MAIN FEED-WATER CONTROL VALVE
- Journal of Mechanical Strength Vol. 37, Issue 5, Pages: 910-916(2015)
- 作者机构：
  
  1. 杭州电子科技大学机械工程学院
  2. 浙江三方控制阀股份有限公司
  3. 环境保护部核与辐射安全中心
- 作者简介：
- 基金信息：
- DOI：10.16579/j.issn.1001.9669.2015.05.023
  CLC：
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LIU QingMin, GAO ZhaoJie, LIN Feng, et al. PERFORMANCE EVALUATION TECHNIQUES FOR THE NUCLEAR GRADE MAIN FEED-WATER CONTROL VALVE. [J]. 37(5):910-916(2015)
DOI：

LIU QingMin, GAO ZhaoJie, LIN Feng, et al. PERFORMANCE EVALUATION TECHNIQUES FOR THE NUCLEAR GRADE MAIN FEED-WATER CONTROL VALVE. [J]. 37(5):910-916(2015) DOI： 10.16579/j.issn.1001.9669.2015.05.023.

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。

Abstract

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.

关键词

有限元核二级主给水控制阀性能评估

Keywords

FEMNuclear safety Class IIFeed-water control valvePerformance evaluation

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