原子能科学技术Issue(11)：2053-2058,6.DOI:10.7538/yzk.2013.47.11.2053
ATHLET程序的钠冷快堆应用扩展及其验证
Modification and Validation of ATHLET Code for Sodium-cooled Fast Reactor Application
摘要
Abstract
System analysis code is important for the global simulation of the sodium-cooled fast reactor (SFR) system as well as transient and accident safety analysis .In this paper ,the best estimate system code ATHLET for light water reactors ,developed by Gesellschaft für Anlagen-und Reaktorsicherheit (GRS) in Germany ,was modified for SFR application .Thermal-dynamic and transport properties as well as heat transfer correlations for sodium were implemented into the ATHLET code .The modified code was then applied to simulate the Phenix reactor in France ,and validation of the code was conducted with the Phenix reactor natural convection test .The calculation results were compared with the test data .The results show that the modified ATHLET code has good applicability in simulating SFR systems .关键词
钠冷快堆/ATHLET程序/自然对流Key words
sodium-cooled fast reactor/ATHLET code/natural convection分类
能源科技引用本文复制引用
周翀,Klaus Huber,程旭..ATHLET程序的钠冷快堆应用扩展及其验证[J].原子能科学技术,2013,(11):2053-2058,6.基金项目
欧盟第七框架“热工水力先进反应堆系统”资助项目 （）
