Experimental and numerical transient analysis of Tehran Research Reactor (TRR)

Abstract

In this paper, a numerical model is presented to analyze a series of reactivity insertion and loss of flow transients in TRR. The model predictions are compared with the experimental data and PARET code results. The model uses the piecewise constant method and the lumped parameter methods for the coupled point kinetics and thermal-hydraulics modules, respectively. The advantages of the piecewise constant method are simplicity, efficiency and accuracy. A main criterion for the applicability range of this model is that the exit coolant temperature remains below the saturation temperature, i.e. no bulk boiling occurs in the core. The calculated values of power and coolant temperature, in both positive reactivity insertion and loss of flow scenario’s, are in good agreement with the experiment values. However, the model is a useful tool for the transient analyses of most researches encountered in reactors in practice. The main objective of this work is using simple calculation methods and benchmarking them with the experimental data. This model can also be used for training purposes.

Keywords

• tehran research reactor
• thermal-hydraulic
• reactivity insertion
• loss of flow