Title of Paper:
Development of TSAC1.0 and application to reactivity insertion accident of CARR
Journal:
Progress in Nuclear Energy
Summary:
In this study, we have developed a thermo-hydraulic and safety analysis code named TSAC1.0 with Visual
Fortran 6.5 to analyze the thermal-hydraulic characteristics of the China advanced research reactor
(CARR) under reactivity insertion accident (RIA) which was induced by unexpected control rod withdrawal
in full power condition. The neutron kinetic model depended on the point kinetics with six
groups of delayed neutrons including reactivity feedback effects and it was adopted for the solution of
reactor power. Furthermore, a new simple and convenient model was adopted for the solution of the
transient behaviors of main pump instead of the complicated four-quadrant model. Visual input, realtime
processing and dynamic visualization output were achieved using Microsoft Visual Studio.NET 2003
to make the application of TSAC1.0 much more convenient in the engineering. The simulated results of
TSAC1.0 were found to be in reasonable agreement with those of RELAP5/MOD3 and showed that the
parameters, including the peak coolant temperature, the peak heat structure temperature, and MDNBR,
were in the acceptable range of design safety limit under RIA.
Co-author:
Ronghua Chen, G.H. Su, Wenxi Tian et al
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