Simulation of the Syrian Miniature Neutron Source Reactor for training operators on the analysis of its anticipated operational accidents

For the purpose of training operators and other educational aspects, a mathematical model capable of assessing potential accidents and safety implications of the research Miniature Neutron Source Reactor (MNSR) has been developed. The model considers relevant physical phenomena that govern the core such as reactor kinetics, reactivity feed-backs due to coolant temperature and xenon, and thermal hydraulics. Natural convection and point kinetics including the prompt jump and complete mixing approximations were employed. Peak power, reactivity core load, core outlet temperature, and other variables are predicted during self-limiting power excursions. Compared to related references, close results have been obtained. The simulating model proves to be a useful tool to train operators and students to assess qualitatively the transient behaviour of the MNSR as a result of sudden reactivity insertion in the core. In addition, the model was utilized to verify some of the design basis accidents already presented in both the Safety Analysis Report (SAR) and the Commissioning Report (CR) of the reactor, as can be seen in Table 1. Furthermore, the dynamic model generates other core variables that are of interest to update the SAR on one side, and confirms others measured and reported in the CR. (author)