Simulation and analysis of IAEA benchmark transients

A simulation model is developed to simulate the coupled kinetics and thermal-hydraulics of Material Testing Reactors (MTR) with simple means. The developed model is used to analyze the series of benchmark transients specified for IAEA 10 MW research reactor. The computed results for ramp positive reactivity insertion and loss of coolant flow transients with scram are presented and discussed. The model predictions are compared with the calculations conducted in various institutions using different codes. It is shown that the model can provide accurate predictions as long as the clad temperature remains below the onset of the nucleate boiling temperature. However, the results are very encouraging and the model is useful for the analysis of most research reactors encountered in practice.