Abstract :
The WIMSD4 code was used to calculate the fast neutron flux spectrum and the fast neutron fission cross-sections for 238U, using six energy groups ranging from 0.5 to 10 MeV. These results, with the measured radioactivities of the 140Ba, 131I, 103Ru, 95Zr and 97Zr fission products emerging from the fission of the 238U foil covered with a cadmium filter, were used to measure the fast neutron flux in the Syrian Miniature Neutron Source Reactor inner irradiation site.
