Calculation of the power distribution in the fuel rods of the low power research reactor using the MCNP4C code

Deterministic evaluation of safety parameters and neutron flux spectra in the MNSR research reactor using DRAGON-4 code

“…This model consisted of all the reactor components which were: 347 fuel rods, four tie rods, three dummy rods for LEU or 7 dummy rods for HEU, control rod and its guide tube, reactor vessel, top and bottom aluminum alloy grids, annular beryllium reflector, bottom beryllium reflector, five inner and five outer irradiation sites and the reactor pool. All the fuel elements, beryllium reflector and the irradiation sites have been represented as cylinders of suitable materials and dimensions positioned at specific location in the model (Dawahra & Khattab, 2011). Fig.1.…”

A comparative study of the neutron flux spectra in the MNSR irradiation sites for the HEU and LEU cores using the MCNP4C code

“…The F5 tally, (x y z R 0 ), was used to calculate the neutron flux for 69 energy groups in the first inner and outer irradiation sites at a depth equals to 15 cm from the top of the reactor core and at radii equal to 16.5 cm and 24.8 cm from the MNSR core centre. The scaling factor in units of fission neutrons per time was calculated for the MNSR reactor and found to be 15 2.224 10 S  (Dawahra et al, 2011). The number of energy groups, energy and energy width which were used in these calculations can be seen in Table 2.…”

Extending the maximum operation time of the MNSR reactor

“…The scaling factor in units of fission neutrons per time was calculated for the MNSR reactor and found to be (Dawahra et al, 2011). The neutron energy flux spectra for each energy group were calculated by dividing the neutron flux by the width of each energy group.…”