Abstract
The paper presents the results of computational neutron-physical modeling of irradiation devices ID-M and WF containing fuel from VVER-1000, APR-1400, and HPR-1000 reactors and placed within the central experimental channel of the IGR reactor. Using the MCNP code system, calculations of the uranium-water ratio, specific power generation distributions in fuel rods, and average specific power along the active fuel height were performed. An analysis of the influence of the design features of single-wall and double-wall irradiation devices on the neutron-physical characteristics of the fuel was carried out. It was established that the use of the double-wall ID-M irradiation device results in approximately a 45% reduction in the average specific power generation level compared to the single-wall WF device. Comparison of the calculated characteristics of the irradiation devices with the corresponding parameters of VVER-1000, APR-1400, and HPR-1000 reactors demonstrated the possibility of reproducing in the IGR reactor power generation levels characteristic of fuel operation in commercial power reactors. The obtained results can be applied to the preparation of in-reactor testing of advanced nuclear fuels, thermal regime assessment, and safety assurance of experimental investigations.