中国科学技术大学学报 ›› 2020, Vol. 50 ›› Issue (4): 428-435.DOI: 10.3969/j.issn.0253-2778.2020.04.006

• 论著 • 上一篇    下一篇

钠冷快堆蒸汽发生器内钠水反应事故的仿真方法

向阳,谭超,陈云龙,祝家银,余述文,赵平辉   

  1. 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
  • 收稿日期:2019-04-01 修回日期:2019-05-22 接受日期:2019-05-22 出版日期:2020-04-30 发布日期:2019-05-22
  • 通讯作者: 赵平辉
  • 作者简介:向阳,男,1993年生,硕士.研究方向:核科学与技术,反应堆工程.E-mail: nexy@mail.ustc.edu.cn

Simulating method of sodium-water reaction accident in steam generator of sodium-cooled fast reactor

XIANG Yang, TAN Chao, CHEN Yunlong, ZHU Jiayin, YU Shuwen, ZHAO Pinghui   

  1. 1.School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 260026, China; 2.Research Institute of Nuclear Power Operation,China National Nuclear Corporation, Wuhan 430074, China
  • Received:2019-04-01 Revised:2019-05-22 Accepted:2019-05-22 Online:2020-04-30 Published:2019-05-22

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.

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

Abstract: 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.

Key words: numerical reactor, sodium-water reaction accident, security analysis of nuclear reactor, sodium cooled fast reactor

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