Abstract

Prior to the commissioning of the IVG.1M reactor with low-enriched uranium fuel, experimental studies of reactor characteristics were carried out on physical and energy start-ups, which should confirm the results of preliminary computational studies and the operability of the reactor. This article is devoted to the study of the axial and radial energy release profile in the IVG.M reactor fuel assemblies using in-reactor dosimetry techniques. The experimental results are compared with the results of neutron-physical simulations. The obtained energy release irregularity coefficients can be used in further thermo-technical calculations.

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