title: Measurement of the fast neutron flux in the MNSR inner irradiation site.
abstract: The WIMSD4 code was used to calculate the fast neutron flux spectrum and the fast neutron fission cross-sections for (238)U, using six energy groups ranging from 0.5 to 10 MeV. These results, with the measured radioactivities of the (140)Ba, (131)I, (103)Ru, (95)Zr and (97)Zr fission products emerging from the fission of the (238)U foil covered with a cadmium filter, were used to measure the fast neutron flux in the Syrian Miniature Neutron Source Reactor inner irradiation site.
authors.affiliation: Nuclear Engineering Department, Atomic Energy Commission, P.O. Box 6091, Damascus, Syria. kkhattab@aec.org.sy
authors.forename: K
authors.initials: K
authors.lastname: Khattab
mesh_terms: D000465:Algorithms; D019544:Equipment Failure Analysis / Q000379:methods*; D005214:Fast Neutrons; D009688:Nuclear Reactors / Q000295:instrumentation*; D011829:Radiation Dosage; D011834:Radiation Monitoring / Q000379:methods*; D012984:Software; D013593:Syria