RELAP5铅铋快堆模型拓展及验证  

RELAP5 Modification and Verification for Lead-bismuth Fast Reactor

作　　者：张家心 王成龙[1] 赵寒冰 张大林[1] 苏光辉[1] 秋穗正[1] 田文喜[1] ZHANG Jiaxin;WANG Chenglong;ZHAO Hanbing;ZHANG Dalin;SU Guanghui;QIU Suizheng;TIAN Wenxi(School of Nuclear Science and Technology,Xi’an Jiaotong University,Xi’an 710049,China;Nuclear Power Institute of China,Chengdu 610041,China)

机构地区：[1]西安交通大学核科学与技术学院,陕西西安710049 [2]中国核动力研究设计院,四川成都610041

出　　处：《原子能科学技术》2021年第7期1260-1267,共8页Atomic Energy Science and Technology

基　　金：科技部重点研发计划(2019YFB1901300)。

摘　　要：为研究铅铋快堆瞬态热工水力特性,对RELAP5程序进行二次开发,添加铅铋合金(LBE)物性模型和液态金属流动换热模型,并与NACIE-UP和CIRCE-ICE台架的实验结果进行对比。计算结果表明:NACIE-UP台架稳态流量和温度相对误差在2%以内,瞬态相对误差不超过5%,与其他系统程序CATHARE、ATHLET、RELAP5-3D、RELAP5/MOD3.3(modified)相比,本文程序的相对偏差不超过10%;CIRCE-ICE台架稳态流量和温度相对误差在2%以内,瞬态相对误差不超过10%。本文程序满足反应堆系统热工水力分析程序精度要求,可作为铅铋快堆安全分析的有效工具。To study the transient thermal-hydraulic characteristics of the lead-bismuth fast reactor,the system thermal-hydraulic analysis code RELAP5 was modified with lead-bismuth eutectic(LBE)properties and heat transfer models.Verification using the NACIE-UP facility and the CIRCE-ICE facility was completed.The calculation results show that the steady-state relative error and transient relative error for the NACIE-UP facility are within 2%and 5%respectively.And compared with other system thermal-hydraulic analysis codes,such as CATHARE,ATHLET,RELAP5-3 D and RELAP5/MOD3.3(modified),the relative deviation is within 10%.The steady-state relative error and transient relative error for the CIRCE-ICE facility are within 2%and 10%respectively.This code can meet the accuracy requirements of thermal-hydraulic analysis code of reactor system,and can be used as an effective tool for safety analysis of lead bismuth fast reactor.

关 键 词：RELAP5程序 液态铅铋合金 模型拓展 验证 

分 类 号：TL334[核科学技术—核技术及应用]