原子能科学技术2016，Vol.50Issue(2)：198-203,6.DOI:10.7538/yzk.2016.50.02.0198
池式钠冷快堆系统分析程序开发
Development of Pool-type Sodium-cooled Fast Reactor System Analysis Code
王晋 1张东辉 1胡文军1
作者信息
- 1. 中国原子能科学研究院快堆研究设计所，北京 102413
- 折叠
摘要
Abstract
According to the characteristics of pool‐type sodium‐cooled fast reactor ,and with the fast reactor hydraulic model , thermal model and neutron kinetics model thoroughly classified and developed ,a fast reactor system analysis code (FASYS code) was developed by FORTRAN95 language for pool‐type sodium‐cooled fast reactor acci‐dent analysis .Transient conditions in CEFR were calculated with FASYS code and the results were used for code validation .The calculation results are consistent with the test data and other fast reactor system analysis code results , and the correctness of the FASYS code is proved .关键词
池式钠冷快堆/系统分析程序/程序开发Key words
pool-type sodium-cooled fast reactor/system analysis code/code develop-ment分类
能源科技引用本文复制引用
王晋,张东辉,胡文军..池式钠冷快堆系统分析程序开发[J].原子能科学技术,2016,50(2):198-203,6.
