Determination of Neutron Flux Distribution along the Dry-Channel of the MNSR Reactor and Determination of Neutron Energy Spectrum in this Reactor

In this work, the relative neutron flux was determined experimentally using neutron activation analysis (NAA) method along the length of the dry channel (GUIDE TUBE) of the Isfahan miniature neutron source reactor (MNSR). This reactor was also simulated using the MCNP code, and the neutron flux distribution along the dry channel was calculated and the results were compared with the measured values. The results showed that the neutron flux distribution peak in the dry channel occurs at a point below the nearest point to the center of the reactor core. This is due to presence of the bottom beryllium reflector. In addition, the simulation program was used to determine the neutron energy spectrum in the dry channel and also in the inner and outer irradiation channels of the reactor. Furthermore, the neutron energy spectrum in an inner irradiation channel of the reactor was compared with the previous studies.