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Volume 31 Issue 2
Apr.  2010
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WU Yingwei, ZHUANG Chengjun, SU Guanghui, QIU Suizheng. Transient Thermal-Hydraulic Characteristics Analysis Software for PWR Nuclear Power Systems[J]. Nuclear Power Engineering, 2010, 31(2): 47-49,62.
Citation: WU Yingwei, ZHUANG Chengjun, SU Guanghui, QIU Suizheng. Transient Thermal-Hydraulic Characteristics Analysis Software for PWR Nuclear Power Systems[J]. Nuclear Power Engineering, 2010, 31(2): 47-49,62.

Transient Thermal-Hydraulic Characteristics Analysis Software for PWR Nuclear Power Systems

  • Received Date: 2008-12-26
  • Rev Recd Date: 2009-06-24
  • Available Online: 2025-07-29
  • Publish Date: 2010-04-01
  • A point reactor neutron kinetics model,a two-phase drift-flow U-tube steam generator model,an advanced non-equilibrium three regions pressurizer model,and a passive emergency core decay heat-removed system model are adopted in the paper to develop the computerized analysis code for PWR transient thermal-hydraulic characteristics,by Compaq Visual Fortran 6.0 language.Visual input,real-time processing and dynamic visualization output are achieved by Microsoft Visual Studio.NET language.The reliability verification of the soft has been conducted by RELAP 5,and the verification results show that the software is with high calculation precision,high calculation speed,modern interface,luxuriant functions and strong operability.The software was applied to calculate the transient accident conditions for QSNP,and the analysis results are significant to the practical engineering applications.

     

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