您当前的位置：
首页 >
文章列表页 >
Impact analysis of basic burnup cross section on coupled calculation of neutron transport burnup
SPECIAL SECTION ON THE 11TH NATIONAL CONFERENCE ON NEW AND RESEARCH REACTORS (PART I) | 更新时间：2024-10-25
|

    • Impact analysis of basic burnup cross section on coupled calculation of neutron transport burnup

    • “In the field of nuclear energy, experts use the MCBMPI program to verify the VERA burnup benchmark problem, analyze the impact of different burnup section libraries on calculations, and provide reference for nuclear reactor design.”
    • NUCLEAR TECHNIQUES   Vol. 43, Issue 4, Article number: 040004(2020)

    • DOI：10.11889/j.0253-3219.2020.hjs.43.040004    

      CLC： TL99

    • Received：16 January 2020，

      Revised：22 February 2020，

      Published：15 April 2020

    移动端阅览

  • YANG Wankui,YUAN Baoxin,HUANG Huan,et al.Impact analysis of basic burnup cross section on coupled calculation of neutron transport burnup[J].NUCLEAR TECHNIQUES,2020,43(04):19-24. DOI： 10.11889/j.0253-3219.2020.hjs.43.040004.

  •  
  •  

0

Views

26

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

No data

Related Author

No data

Related Institution

No data
0