Transient test of a NSSS thermal-hydraulic module for the nuclear power plant simulator using a best-estimate code, RETRAN

被引：0
|
作者：
Lee, MS
Seo, IY
Kim, YH
Lee, YK
Suh, JS
机构：
[1] Korea Elect Power Res Inst, Taejon, South Korea
[2] Future & Challenge Tech, Seoul, South Korea
来源：
SYSTEMS MODELING AND SIMULATION: THEORY AND APPLICATIONS | 2005年 / 3398卷
关键词：
D O I：
暂无
中图分类号：
TP18 [人工智能理论];
学科分类号：
081104 ; 0812 ; 0835 ; 1405 ;
摘要：
Korea Electric Power Research Institute (KEPRI) developed real-time simulation Thermal hydraulic model (ARTS) which is based on the best-estimate code, RETRAN. It was adapted Kori unit 1 nuclear power plant analyzer (NPA). This paper describes the result of the some of steady and transient tests of the Kori unit 1 NPA. The simulated results are compared and reviewed with the plant data and calculated reference data.
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页码：529 / 535
页数：7
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