Filters
Results 1 - 1 of 1
Results 1 - 1 of 1.
Search took: 0.021 seconds
Sabitova, R. R.; Popov, Yu A.; Irkimbekov, R. A.; Prozorova, I. V.; Svetachev, S. N.; Medetbekov, B. S.; Bedenko, S. V., E-mail: sabitovar@nnc.kz
Sociedad Mexicana de Irradiacion y Dosimetria, Ciudad de Mexico (Mexico). Funding organisation: Universidad Autonoma Metropolitana, Unidad Iztapalapa (Mexico); Universidad Autonoma de Zacatecas Francisco Garcia Salinas (Mexico); Instituto Nacional de Investigaciones Nucleares (Mexico); Federacion de Radioproteccion de America Latina y el Caribe (Mexico)2022
Sociedad Mexicana de Irradiacion y Dosimetria, Ciudad de Mexico (Mexico). Funding organisation: Universidad Autonoma Metropolitana, Unidad Iztapalapa (Mexico); Universidad Autonoma de Zacatecas Francisco Garcia Salinas (Mexico); Instituto Nacional de Investigaciones Nucleares (Mexico); Federacion de Radioproteccion de America Latina y el Caribe (Mexico)2022
AbstractAbstract
[en] For the past ten years, the IVG.1M research reactor has been converted from HEU fuel to LEU fuel. Currently, the final stages of conversion (physical and energy start-ups of reactor) are being carried out. One of the tasks of physical start-up was to conduct physical studies of power distribution by radius and height of 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-products or activation products. Study object was activation of indicators from copper wire and fuel element fragments placed in physical mock-up of technological channels with LEU fuel. ENREDI program, based on polynomial interpolation and approximation methods, was used to determine the detailed (in each fuel elements) relative power distribution by radial cross section of fuel assembly. During these experimental studies, relative power distribution over the height and radial cross section of technological channels of each rows, power peaking factors and value of absolute power were obtained. These studies will make it possible to evaluate changes in power profile in the IVG.1M reactor fuel after reducing of the enrichment, and also to check the accuracy of neutronic simulation. (author)
Primary Subject
Source
Oct 2022; 15 p; Sociedad Mexicana de Irradiacion y Dosimetria; Zacatecas, Zac. (Mexico); ISSSD 2022: 22. international symposium on solid state dosimetry; Zacatecas, Zac. (Mexico); 19-23 Sep 2022
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
ACTINIDES, CALCULATION METHODS, DIMENSIONS, ELECTROMAGNETIC RADIATION, ELEMENTS, ENERGY SOURCES, ENRICHED URANIUM, FUELS, FUNCTIONS, INFORMATION, IONIZING RADIATIONS, ISOTOPE ENRICHED MATERIALS, ISOTOPES, MATERIALS, MATHEMATICAL SOLUTIONS, METALS, NEUTRAL-PARTICLE TRANSPORT, NUMERICAL SOLUTION, RADIATION TRANSPORT, RADIATIONS, RADIOACTIVE MATERIALS, REACTOR COMPONENTS, REACTOR LIFE CYCLE, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, START-UP, TRANSITION ELEMENTS, URANIUM
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue