Numerical and experimental characterization of the reaction rates in the core of the CNESTEN’s TRIGA Mark II research reactor

Education, training and isotopes production are the most important uses of Moroccan 2 MW TRIGA Mark II reactor situated at National Center for Energy Sciences Nuclear Techniques (CNESTEN, Morocco). To develop new R&D projects in research reactors, particular advanced knowledge neutron photon flux distribution, within around core, is crucial. In order to precisely preparing experiments CNESTEN’s reactor, a detailed model was developed using 3D continuous energy Monte Carlo code TRIPOLI-4 cross-section data from JEFF3.1.1 nuclear library. This used carry out preliminary calculations estimate levels irradiation channels as well calculate kinetic parameters core excess reactivity, integral control rods worth power peaking factors. As first step validation model, obtained results were compared with experimental ones available Final Safety Analysis Report (FSAR) reactor. A study being carried end which will be published an evaluated benchmark. Furthermore, this work aims experimentally characterize reaction rates various inside outside core. The measurements activation technique. set up design series performed expected gamma flux/intensity materials after irradiations different positions facilities. Different foils known characteristics then irradiated activity several measured Gamma Spectrometry Method. relative calculated through model. Fairly good agreement found, indicates that computational accurate enough reproduce experiments.