TY - JOUR
T1 - Transient thermal-hydraulic characteristics analysis software for pwr nuclear power systems
AU - Wu, Ying Wei
AU - Zhuang, Cheng Jun
AU - Su, Guang Hui
AU - Qiu, Sui Zheng
PY - 2010/4
Y1 - 2010/4
N2 - 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.
AB - 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.
KW - Dynamic visualization
KW - Nuclear power system
KW - PWR
KW - Transient characteristics
KW - Visual input
UR - https://www.scopus.com/pages/publications/77952644194
M3 - 文章
AN - SCOPUS:77952644194
SN - 0258-0926
VL - 31
SP - 47-49+62
JO - Hedongli Gongcheng/Nuclear Power Engineering
JF - Hedongli Gongcheng/Nuclear Power Engineering
IS - 2
ER -