Development and validation of thermal-hydraulic and safety analysis code for CARR (TSACC)

被引：0
|
作者：
Tian, Wen-Xi [1 ]
Qiu, Sui-Zheng [1 ]
Su, Guang-Hui [1 ]
Jia, Dou-Nan [1 ]
Liu, Xing-Min [2 ]
Zhang, Jian-Wei [2 ]
机构：
[1] State Key Laboratory of Multi-Phase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an 710049, China
[2] China Institute of Atomic Energy, Beijing 102413, China
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2009年 / 30卷 / 01期
关键词：
Heat transfer - Nuclear fuels - Nuclear reactor accidents - Codes (symbols) - Nuclear energy;
D O I：
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学科分类号：
摘要：
A Thermal-hydraulic and Safety Analysis Code for CARR (TSACC) was developed using Fortran Language. The adoption of modular programming techniques enables TASCC to be applied to other reactors by easily modifying the corresponding function modules. Based on the principle of code validation, the Loss of Off-site Power (LOP) accident was analyzed using both TSACC and RELAP5/Mod3. Some important thermal-hydraulic parameters, such as coolant flowrate, temperature and MDNBR, in the mean channel and hot channel were obtained. The comparison between the computation results by TSACC and RELA5/Mod3 showed a good agreement in spite of a little larger difference during the coolant inverse flow process. The larger local difference is mainly caused by the adoption of different heat transfer correlations under low flow condition in the two codes. The code validation proves the applicability and accuracy of TSACC.
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页码：40 / 44
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