Thermal-hydraulic analysis of VVER-1000 reactor during LOFA
Thermal-hydraulic analysis of VVER-1000 reactor during LOFA
Kamran Sepanloo1 Ehsan Zarifi2 Saman Tashakor3
1) Nuclear Science and Technology Research Institute, Tehran,
2) Nuclear Science and Technology Research Institute, Tehran,
3) Department of Nuclear Engineering, Shiraz Branch, Islamic Azad University, Shiraz,
Publication :
International Conference on Engineering and Applied Science(iceasconf.com)
Abstract :
The Loss Of Flow Accident (LOFA) is one of the most important Design Basis Accidents (DBA) in the reactor analysis. A loss of coolant flow can occur from mechanical failure or power supply which could cause a reduction in flow. This paper provides a transient thermal-hydraulic model of VVER-1000 reactor during LOFA by RELAP5 code. The obtained results from the RELAP5 transient analysis showed a reasonable agreement with the Bushehr NPP Final Safety Analysis Reports (FSAR). Also the results show that by effective function of protection systems in the beginning of the accident, the reactor maintains its safety margin.
Keywords :
LOFA
thermal-hydraulic analysis
RELAP5 code
VVER-1000 reactor