Computational-Experimental Investigation of the Special Features of the Neutron Spectrum of an IGR Reactor

The energy spectra of neutrons in the experimental channel of an IGR reactor were measured using neutron-activation detectors. Ten detectors for thermal and intermediate neutrons, eight thresholds, and four fission detectors were used. The thermal-neutron fluence was calculated using the standard methods of reactor dosimetry, and the intermediate and fast neutron spectra were reconstructed using a special program. The experimental data essentially confirmed the computational results. 2 figures, 2 tables, 11 references.