检索规则说明:AND代表“并且”;OR代表“或者”;NOT代表“不包含”;(注意必须大写,运算符两边需空一格)
检 索 范 例 :范例一: (K=图书馆学 OR K=情报学) AND A=范并思 范例二:J=计算机应用与软件 AND (U=C++ OR U=Basic) NOT M=Visual
作 者:向阳 谭超 陈云龙 祝家银 余述文 赵平辉[1] XIANG Yang;TAN Chao;CHEN Yunlong;ZHU Jiayin;YU Shuwen;ZHAO Pinghui(School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 260026, China;Research Institute of Nuclear Power Operation,China National Nuclear Corporation, Wuhan 430074, China)
机构地区:[1]中国科学技术大学核科学技术学院,安徽合肥230026 [2]中核集团核动力运行研究所,湖北武汉430074
出 处:《中国科学技术大学学报》2020年第4期428-435,共8页JUSTC
摘 要:钠冷快堆钠水反应事故的仿真是钠冷快堆仿真机开发的一个难点.为了解决这个问题,基于钠冷快堆蒸汽发生器内传热管水泄漏导致的钠水反应事故的数学物理方程,设计了一个钠水反应事故的模拟程序.使用SimTherm热工水力仿真程序,针对钠冷快堆的结构,设计了适用于钠水反应事故研究的钠冷快堆二回路模型.通过将钠水反应事故模拟程序与SimTherm进行耦合运行,实现了钠冷快堆钠水反应事故的仿真,为钠冷快堆仿真机的开发提供了一种新的思路.The simulation of sodium-water reaction accident is the difficulty in the development of the simulating system of sodium cooled reactor.In order to solve this problem,a simulation program of sodium-water reaction accident was designed based on the mathematical physical equation of sodium-water reaction accident caused by water leakage in heat transfer tube of sodium-cooled fast reactor steam generator.Based on SimTherm thermal-hydraulic simulation program and the structure of sodium-cooled fast reactor,a second-circuit model of sodium-cooled fast reactor was designed for the study of sodium-water reaction accidents.By coupling the simulation program of sodium-water reaction accident with SimTherm,the simulation of sodium-water reaction accident was realized,which provides a new idea for the development of sodium-cooled fast reactor simulator.
关 键 词:数值反应堆 钠水反应事故 反应堆安全分析 钠冷快堆
分 类 号:TL353.13[核科学技术—核技术及应用] TL33
正在载入数据...
正在载入数据...
正在载入数据...
正在载入数据...
正在载入数据...
正在载入数据...
正在载入数据...
正在链接到云南高校图书馆文献保障联盟下载...
云南高校图书馆联盟文献共享服务平台 版权所有©
您的IP:216.73.216.7