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作 者:杨宗昊 马权[1] 刘明明[1] 武有光 王恺 YANG Zonghao;MA Quan;LIU Mingming;WU Youguang;WANG Kai(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu 610213,China)
机构地区:[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610213
出 处:《自动化仪表》2021年第S01期168-172,共5页Process Automation Instrumentation
摘 要:后备盘(BUP)主要作为核电厂主控制室数字化技术失效后的备用手段,用于安全停堆并将反应堆维持在冷停堆水平以及事故工况下处理。后备盘实现报警、显示和控制三类功能,其安全、可靠性对于保障反应堆安全停堆十分重要。开展对核电厂后备盘的辐射散热以及自然对流的热分析模拟,定量地对辐射换热以及自然对流在后备盘中所起的作用进行分析说明,掌握后备盘散热的机理。研究结果表明,通过仿真模拟得到的后备盘内部的最高温度在为60℃,满足电源模块最高运行温度70℃的要求;后备盘散热过程中辐射换热过程占据较大的比例,辐射换热与自然对流的比例大概为6∶1,空气自然对流对机柜本身造成的温升可以忽略;真实后备盘内部的结构件与线缆对自然循环散热以及辐射换热所造成的影响可以忽略。该研究结果与经验可以为复杂工况下的核动力仪控设备的散热分析提供参考。The backup panel(BUP)is mainly used as a backup means after the failure of digital technology in the main control room of nuclear power plant,which is used to safely shut down the reactor and maintain the reactor at the cold shutdown level and deal with the accident conditions.BUP panel equipment can realize alarm,display and control functions,and its safety and reliability are very important to ensure the safety of reactor shutdown.Thermal analysis and simulation of radiation heat dissipation and natural convection of BUP panel are carried out.The role of radiation heat dissipation and natural convection in BUP panel are quantitatively analyzed,so as to grasp dissipation mechanism of BUP panel.The research results show that the maximum temperature inside the BUP panel obtained by simulation is 60℃,which satisfies the requirement of the maximum operating temperature of the power module is 70℃.The radiation heat transfer process takes up a large proportion in the heat dissipation process of BUP panel,and the ratio between radiation heat transfer and natural convection is about 6:1.The temperature rise caused by natural convection of air to the cabinet itself can be ignored.The influence of structural devices and cables inside the real BUP panel on natural convection and radiation can be also ignored.The research results and experience can provide reference for the heat dissipation analysis of nuclear power instrument and control devices under complex working conditions.
关 键 词:核电厂 主控室 后备盘 自然对流 辐射换热 散热分析 机理研究 计算流体力学
分 类 号:TH89[机械工程—仪器科学与技术]
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