核级高压气体减压阀设计与试验

Design and Test of Nuclear High Pressure Gas Pressure Reducing Valve

介绍了抗震Ⅰ类核级高压气体减压阀的理论计算、结构设计、抗震分析和试验方法。对于非标准压力-温度等级工况,根据ASME B16.34标准采用矩阵插值法计算得出中间压力磅级标号和常温下水压试验压力,通过插值法计算阀体最小壁厚值。根据气体质量流量方程和临界压力比计算不同减压比下的最小阀座流通面积。采用双级并联和模块化单元设计,并将气体高压进行优化分级减压处理,保持高压差工况下减压性出口压力稳定。利用ANSYS有限元软件,对阀门进行模态分析和强度计算,并根据ASME BPVC-Ⅲ规范对计算结果进行应力评定。根据核级减压阀的技术规范和鉴定大纲要求,自主设计与构建减压阀气体测试装置,并编制试验规程,完成各项型式试验项目。为核级高压气体减压阀的安全应用提供了保证,同时为类似核电阀门产品的设计开发提供参考。

This paper introduces the theoretical calculation,structural design,seismic analysis and test methods of the anti-seismic class Ⅰ nuclear high-pressure gas pressure reducing valve.For non-standard pressure temperature rating conditions,according to ASME B16.34 standard,this paper uses matrix interpolation method to calculate the intermediate pressure grade and hydro-static test pressure under normal temperature,and calculates the minimum wall thickness of valve body through interpolation method.According to the gas mass flow equation and the critical pressure ratio,the minimum valve seat flow area under different pressure reduction ratios is calculated.The two-stage parallel connection and modular unit design are adopted,and the gas high pressure is optimized and graded for pressure reduction,so as to maintain the stable outlet pressure under the condition of large span high pressure difference.ANSYS finite element analysis software is used to carry out modal analysis and strength calculation for the valve,and stress evaluation is carried out for the calculation results according to ASME BPVC-Ⅲ code.According to the technical specifications and qualification outline requirements of nuclear pressure reducing valves,the gas testing device of pressure reducing valves is independently designed and constructed,and the test procedures are prepared,and various type test items are completed.The calculation process and test method described in this paper provide a guarantee for the safe application of nuclear grade high-pressure gas pressure reducing valve,and also provide a useful reference for the design and development of similar nuclear power valve products.