您当前的位置：
首页 >
文章列表页 >
Unprotected loss of flow condition analysis of sodium cold fast reactor based on lumped parameter method
NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2024-10-25
|

    • Unprotected loss of flow condition analysis of sodium cold fast reactor based on lumped parameter method

    • “In the field of advanced reactor research, experts use the lumped parameter method to establish a primary loop model of a pool type fast reactor, and write a nuclear thermal coupling program based on MATLAB to conduct safety analysis of unprotected flow loss accident conditions. The calculated results are compared with experimental values and other institutional calculation results to verify the reliability of the program.”
    • NUCLEAR TECHNIQUES   Vol. 43, Issue 5, Article number: 050601(2020)

    • DOI：10.11889/j.0253-3219.2020.hjs.43.050601    

      CLC： TL364+.4

    • Received：02 December 2019，

      Revised：21 January 2020，

      Published：15 May 2020

    移动端阅览

  • FANG Peng,YANG Yongwei,ZHAO Zelong.Unprotected loss of flow condition analysis of sodium cold fast reactor based on lumped parameter method[J].NUCLEAR TECHNIQUES,2020,43(05):54-60. DOI： 10.11889/j.0253-3219.2020.hjs.43.050601.

  •  
  •  

0

Views

29

下载量

1

CSCD

Alert me when the article has been cited
提交
Tools
Download
Export Citation
Share
Add to favorites
Add to my album

Related Articles

Steady state performance analysis of lithium heat pipe based on improved lumped parameter model

Related Author

HU Chongju
LI Bin
YU Dali
ZHANG Xiuxiang
MEI Huaping
LI Taosheng
WANG Hongyan

Related Institution

Suzhou University
Institute of Nuclear Safety Technology, Hefei Institutes of Physical Science, Chinese Academy of Sciences
Taiyuan North Permanent Magnet Motor Technology Co., Ltd
0