Monte Carlo modeling of the NUR Nuclear Research Reactor

Abstract

This work deals with the development of a full three-dimensional model tailored for the Algerian light water Nuclear Uranium Reactor (NUR) with the Monte Carlo N-Particle MCNP5 code. Once a satisfactory model was obtained, the criticality and its systematic uncertainty were investigated. Thereafter, important neutronic and safety parameters of this reactor were assessed. In order to check the consistency of the Monte Carlo (MC) model, the fresh core configuration was considered. To avoid additional biases, the calculations were performed for a zero cold power with no poison conditions. The achieved MC results were compared successfully to previous experimental values as well as to data issued from the safety analysis report and other published works. Generally, the present MC model provides an accurate description of the major investigated neutronic parameters and reproduces well the criticality condition of the first operating NUR research reactor core configuration. Finally, with the current model, it would be possible to use it as a basis for future studies under any other reactor core configurations or fuel for any given purposes.