Regarding the fact that pro‎mp‎t gamma neutron activation analysis is a very useful method for material analysis, a decision was made on the feasibility of creating a suitable neutron beam for this facility in the Isfahan research reactor. This reactor is a tank-pool reactor with a maximum power of 30 kW. A suitable neutron beam is one of the important factors in the efficiency of these facilities. According to some considerations, it was decided to choose one of the existing channels inside the reactor tank in order to use the thermal neutron flux. Using the MCNP code, the core of the reactor was simulated and the feasibility of creating this type of beam was investigated. A suitable beam for this facility is a beam that produces a high thermal neutron flux and at the same time low epithermal and fast neutron flux and low photon dose rate in the position of the sample. In order to optimize the neutron beam parameters, it is necessary to make changes such as using a neutron moderator or a gamma filter inside the channel. These changes were simulated using the MCNP code and the results were analyzed. The results of these simulations showed that despite the low power of the Isfahan Miniature Neutron Source Reactor compared to the other facilities, a suitable neutron beam can be applied in the pro‎mp‎t gamma neutron activation analysis facilities with this reactor. Thermal neutron flux and gamma dose at the exit of the channel after using 5 cm of heavy water as a moderator at the inlet of the channel and a bismuth filter with a thickness of 0.5 cm and a cylindrical hole with a diameter of 0.5 cm at the height of 150 cm are 1.64×106 n. cm-2. s-1 and 1.35×10-2 Sv. h-1, respectively.

ظفراله كلانتري , جواد مختاري

ظفراله كلانتري

ظفراله كلانتري , احمد شيراني بيد آبادي