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安全分析程序SAC-PREARS的开发
引用本文:廖义香,张文星,贾斗南,于涛. 安全分析程序SAC-PREARS的开发[J]. 核动力工程, 2003, 24(4): 384-386
作者姓名:廖义香  张文星  贾斗南  于涛
作者单位:1. 南华大学,湖南,衡阳,421001
2. 西安交通大学,710049
基金项目: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-PFI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。

关 键 词:核供热堆 自然循环 余热排除系统 安全分析
文章编号:0258-0926(2003)04-0384-03
修稿时间:2002-06-12

The Development of a Safety Analysis Code SAC——PREARS
LIAO Yi-xiang,ZHANG Wen-xing,JIA Dou-nan,YU Tao. The Development of a Safety Analysis Code SAC——PREARS[J]. Nuclear Power Engineering, 2003, 24(4): 384-386
Authors:LIAO Yi-xiang  ZHANG Wen-xing  JIA Dou-nan  YU Tao
Affiliation:LIAO Yi-xiang1,ZHANG Wen-xing1,JIA Dou-nan2,YU Tao1
Abstract: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.
Keywords:Nuclear heating reactor (NHR)  Natural circulation  Residual-heat-removal System  Safety analysis  
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