摘要
压水堆核电站燃料传输系统的主要功能是将核燃料组件在反应堆厂房和燃料厂房之间进行相互传送。为保障其结构在不同工况下能够安全运行,需对其在异常工况(OBE)和事故工况(SSE)下进行抗震性能分析。为此,采用有限元分析软件ANSYS 12.0对某百万千瓦级核电站的燃料传输系统进行了结构建模;对传输系统在运行过程中不同构型下的转运通道、承载器、传输小车、反应室倾翻架、燃料室倾翻架、燃料室轨道结构和反应室轨道结构等主要构件在不同工况下进行了应力分析;采用SRSS方法进行了应力组合,并依据RCCM规范对各构件进行不同工况下的强度评定。结果表明,在异常和事故工况下,燃料传输系统在不同构型下各结构均满足强度要求,具有良好的抗震性能。
In the PWR nuclear power plant, the function of the fuel transfer system (FTS) is to transfer the fuel assembly between the reactor building and the fuel building. The seismic analysis of the transfer system structure should be carried out to ensure the safety under OBE and SSE. Therefore,the ANASYS 12.0 software is adopted to construct the finite element analysis model for the fuel transfer system in a million kilowatt nuclear power plant. For the various configurations of FTS in the operating process,the stresses of the main structures, such as the transfer tube, fuel assembly container, fuel conveyor car, lifting frame in the reactor building, lifting frame in the fuel building, support and guide structure of conveyor car and the lifting frame in both buildings,are computed. The stresses are combined with the method of square root of square sum (SRSS) and assessed under various seismic conditions based on RCCM code, the results of the assessment satisfy the code. The results show that the stresses of the fuel transfer system structure meet the strength requirement, meanwhile, it can withstand the earthquake well.
出处
《核科学与工程》
CSCD
北大核心
2012年第3期277-283,共7页
Nuclear Science and Engineering
基金
国家能源核电站核级设备研发中心项目
深圳市国家/省级项目配套扶持计划项目
中国广东核电集团<核燃料运输贮存系统(PMC)国产化>项目
关键词
燃料传输系统
有限元模型
抗震分析
强度评定
fuel transfer system
finite element model
seismic analysis
strength assessment