安全分析程序SAC-PREARS的开发  

The Development of a Safety Analysis Code——SAC-PREARS

作　　者：廖义香[1] 张文星[1] 贾斗南[2] 于涛[1] 

机构地区：[1]南华大学,湖南衡阳421001 [2]西安交通大学,710049

出　　处：《核动力工程》2003年第4期384-386,共3页Nuclear Power Engineering

基　　金：国家重点科技攻关项目(96-G01-02-05)

摘　　要：介绍了SAC-PREARS程序的基本数学模型。利用MISAP程序和通用程序TRAC-PF1对SAC-PREARS计算结果进行了验证。结果表明:SAC-PREARS程序能够有效地计算和分析核供热堆PRHRS的稳态和瞬态热工水力特性。The basic mathematic & physical model has been established and the results have been validated by comparing with those of MISAP and the general code TRAC-PF1. The results show that SAC-PREARS can effectively compute and analyze the steady state and transient thermal-hydraulic characteristics of the residual-heat-removal system of NHR.

关 键 词：核供热堆 自然循环 余热排除系统 安全分析 

分 类 号：TL333[核科学技术—核技术及应用] TL413.3