Measurement of the fast neutron flux in the MNSR inner irradiation site

The WIMSD4 code was used to calculate the fast neutron flux spectrum and the fast neutron fission cross-sections for U-238, using six energy groups ranging from 0.5 to 10 MeV. These results, with the measured radioactivities of the Ba-140, I-131, Ru-103, Zr-95 and Zr-97 fission products emerging from the fission of the U-238 foil covered with a cadmium filter, were used to measure the fast neutron flux in the Syrian Miniature Neutron Source Reactor inner irradiation site. (c) 2006 Elsevier Ltd. All rights reserved.