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

作　　者：周翀[1] Klaus Huber 程旭[1] 

机构地区：[1]上海交通大学核科学与工程学院,上海200240 [2]卡尔斯鲁厄理工大学聚变与反应堆技术研究所,德国卡尔斯鲁厄76131

出　　处：《原子能科学技术》2013年第11期2053-2058,共6页Atomic Energy Science and Technology

基　　金：欧盟第七框架"热工水力先进反应堆系统"资助项目(249337)

摘　　要：系统分析程序是对钠冷快堆的冷却剂回路系统进行全局模拟、瞬态及事故安全分析的重要工具。本工作对德国核设施与反应堆安全机构(GRS)开发的轻水堆最佳估算系统程序ATHLET进行修改,增加了钠的物性公式和传热关系式,将其适用范围扩展到钠冷快堆。为验证修改过的ATHLET程序,对法国凤凰(Phenix)反应堆系统建模,并对其自然对流实验进行模拟,将计算结果与实验数据进行比较。结果显示,ATHLET程序的钠冷快堆应用扩展具有良好的适用性。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 far 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 

分 类 号：TL425[核科学技术—核技术及应用]