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Volume 30 Issue 1
Feb.  2009
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TIAN Wen-xi, QIU Sui-zheng, SU Guang-hui, JIA Dou-nan, LIU Xing-min, ZHANG Jian-wei. Development and Validation of Thermal-Hydraulic and Safety Analysis Code for CARR (TSACC)[J]. Nuclear Power Engineering, 2009, 30(1): 40-44.
Citation: TIAN Wen-xi, QIU Sui-zheng, SU Guang-hui, JIA Dou-nan, LIU Xing-min, ZHANG Jian-wei. Development and Validation of Thermal-Hydraulic and Safety Analysis Code for CARR (TSACC)[J]. Nuclear Power Engineering, 2009, 30(1): 40-44.

Development and Validation of Thermal-Hydraulic and Safety Analysis Code for CARR (TSACC)

  • Received Date: 2007-12-08
  • Rev Recd Date: 2008-04-18
  • Available Online: 2025-07-28
  • Publish Date: 2009-02-15
  • A Thermal-hydraulic and Safety Analysis Code for CARR(TSACC) was developed using For-tran Language. The adoption of modular programming techniques enables TASCC to be applied to other re-actors 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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