核电厂主设备用大型液压阻尼器鉴定技术研究

A Study on Qualification Technology of Large Hydraulic Snubbers for Nuclear Power Plants Equipment

针对核电厂主设备用大型液压阻尼器的鉴定技术要求,对国内外核级阻尼器鉴定相关的标准进行了梳理,分析比较了ASME QME-1、KTA 3205.3和NB/T 20036.4标准中对核级阻尼器鉴定要求。针对阻尼器鉴定试验中的刚度测试、使用工况模拟和老化试验次数等问题,进行了进一步探讨。结合《先进轻水反应堆用户要求文件》的要求,提出了核级阻尼器鉴定中刚度测试的一种替代方法;结合核电厂事故条件下环境情况,提出了和级阻尼器使用工况的模拟提出了具体方法;结合核电厂实际运行瞬态情况,提出了老化试验中试验次数的建议。基于核级阻尼器鉴定技术研究结果,给出了核级液压阻尼器鉴定示例。

For the qualification requirements of large hydraulic snubbers for the main equipment in nuclear power plants,the requirements and differences of different standards at home and abroad are analyzed.The requirements of nuclear snubbers qualification in ASME QME-1、KTA 3205.3 and NB/T 20036.4 standards are analyzed and compared.According to the requirements of“Advanced Light Water Reactor Utility Requirements Document”,an alternative method for stiffness testing in nuclear snubber qualification is proposed.According to the environmental conditions of the nuclear power plant under accident conditions,the simulation method of the operating conditions of the snubber is proposed.According to the transient situation of the actual operation of nuclear power plants,the suggestions on the number of tests in the aging test is proposed.Based on the research of nuclear-grade snubber qualification technology,an example of nuclear hydraulic snubber qualification is given.