Experimental studies of power distribution in LEU-fuel of the IVG.1M reactor

For the past ten years, the IVG.1M research reactor has been converted from high-enriched uranium (HEU) fuel to low-enriched uranium (LEU) fuel. Currently, the final stages of the IVG.M reactor conversion, including physical and energy start-ups, are underway. As part of the physical start-up, one o...

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Published inApplied radiation and isotopes Vol. 200; p. 110942
Main Authors Sabitova, R.R., Popov, Yu. A., Irkimbekov, R.A., Bedenko, S.V., Prozorova, I.V., Svetachev, S.N., Medetbekov, B.S.
Format Journal Article
LanguageEnglish
Published England Elsevier Ltd 01.10.2023
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Summary:For the past ten years, the IVG.1M research reactor has been converted from high-enriched uranium (HEU) fuel to low-enriched uranium (LEU) fuel. Currently, the final stages of the IVG.M reactor conversion, including physical and energy start-ups, are underway. As part of the physical start-up, one of the objectives was to conduct physical studies on the power distribution across the radius and height of the fuel assemblies in water-cooled technological channels. Studies were carried out using the activation gamma-spectrometric method based on correspondence between energy release and measured gamma-radiation activity of fission or activation products. The ENREDI program was used to determine the detailed relative power distribution over radial cross section of fuel assembly. During these experimental studies, relative power distribution along the height and radial cross section of the IVG.1M fuel assembly, as well as power peaking factors were obtained. These studies will make it possible to evaluate the changes in the IVG.1M reactor fuel power profile after the fuel enrichment reduction, and to verify the accuracy of neutronic simulations. •The power distribution in the IVG.1M reactor fuel was investigated experimentally.•Comparison of power distribution for LEU and HEU fuels was carried out.•After the reactor conversion, the internal block effect of the fuel increased.•The results can be used for checking the reliability of neutron-physical simulations.
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ISSN:0969-8043
1872-9800
DOI:10.1016/j.apradiso.2023.110942