Feedback reactivity coefficients for the Syrian MNSR research reactor

The feedback reactivity coefficients which account for variation in fuel and moderator temperatures as well as the void coefficient have been calculated using the WIMS-D/4 and CITATION codes for the Syrian MNSR research reactor. The cross sections of all the reactor components at different temperatures were generated using the WIMSD4 code. These group constants were used then in the CITATION code to calculate the multiplication factor and the neutron spectrum at different water and fuel temperatures using 69 energy groups. Only one parameter was changed where all other parameters were kept constant. The calculated feedback coefficients were compared with the measured ones. Good agreements between the measured and calculated feedback reactivity coefficients were obtained.

► The feedback reactivity coefficients have been calculated for the Syrian MNSR.
► The cross sections of the reactor components at different temperatures were generated.
► These group constants were used then in the CITATION code to calculate the keff.