核电厂主泵水力部件运输容器跌落分析研究  

Dropping Analysis and Research on Hydraulic Parts of Main Pump Transport Container in Nuclear Power Plant

作　　者：孙胜[1] 许静[1] 汪海[1] 黄岗[1] 童明炎[1] 

机构地区：[1]中国核动力研究设计院,成都610005

出　　处：《机械工程师》2016年第5期13-16,共4页Mechanical Engineer

摘　　要：主泵是核电厂运行的核心设备之一,为保障核电厂运行安全,主泵的水力部件必须定期送往检修站检修,目前国内还未有该类型的放射性运输容器。结合主泵水力部件运输容器研发项目,依据国内法规和标准要求,利用ANSYS对该运输容器进行跌落分析研究,并采用适宜的评价准则进行评价,验证其强度满足设计要求。该研究为国内首台主泵水力部件运输容器的结构设计和安全分析提供技术支持,同样对其他放射性运输容器设计具有借鉴作用。Main pump is one of core equipments in nuclear power plant, hydraulic parts of main pump must be sent to overhaul station for overhauling regularly to assure the operation safety of nuclear power plant, the radioactive transport container for hydraulic parts of main pump has not been developed at present in China. Based on development project of hydraulic parts of main pump transport container, dropping analysis of the transport container is carried out using ANSYS code according to domestic regulations and standards in the paper, the assessment with suitable rules is also performed to verify the stress and stiffness of the container. The technological support for the structure design and safety analysis of the first hydraulic parts of main pump container is provided due to the research. Furthermore, the research also provides a reference for the structure design of the other radioactive transport container.

关 键 词：主泵 运输容器 

分 类 号：TP391.7[自动化与计算机技术—计算机应用技术]