[en] Benchmark neutronic calculations were carried out for the Syrian Miniature Neutron Source Reactor (MNSR). Ten energy group lattice constant calculations were performed employing WIMSD code while entire core with beryllium reflector and irradiation sites was modeled in CITAION. Calculated neutronic parameters included core excess reactivity, control rod worth, thermal neutron flux at irradiation sites, peaking factors, feed back moderator temperature coefficient of reactivity, and axial and radial profiles for power densities. Calculated values of these parameters were compared with the quoted/published data. Values of calculated excess reactivity, control rod worth and neutron flux at irradiation sites match reasonably well with the published data. However there is some difference between calculated and quoted values of peak power density and moderator temperature coefficient of reactivity. Axial power distribution for different control rod positions is shown. (orig./A.B.)