Transient analysis of MTR research reactor during fast and slow loss of flow accident

Abstract The main objective for reactor safety is to keep the fuel in a safe condition with adequate safety margins during all operational modes (normal-abnormal and accidental states). To achieve this purpose an accident analysis of different design base accidents (DBAs), one of them is the loss of flow accident (LOFA), is required for assessing reactor safety. In this research, the safety aspects of 22 MW MTR research reactor under steady state and during loss of flow accident is studied. The flow transients considered include fast loss of flow accident (FLOFA) and slow loss of flow accident (SLOFA) modeled with exponential flow decay and time constants of 1 and 25 s, respectively. The analysis is done using PARET, a neutronics-hydrodynamics-heat transfer code. The transients were initiated from a full power with a flow trip point at 85% nominal. The calculated parameters are the temperatures of different components (fuel, clad and coolant) as a function of time for the hot channel. The results indicate that in both accidents the calculated maximum cladding surface temperature for the hottest channel of the reactor core does not exceed the allowable safety limit and the fuel integrity is maintained.