Study of Reduced-Enrichment Uranium Fuel Possibility for Research Reactors

Having analyzed the results obtained in the work, it is possible to conclude that the flux density of fast and thermal neutrons in the shell of fuel elements in EFA in REU-zone decreased on average by 5% for UO2 fuel and by 7% for U9%Mo fuel. Change of neutrons flux density during the cycle does not...

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Bibliographic Details
Published in:	MATEC web of conferences Vol. 37; p. 1059
Main Authors:	Ruppel, V.A., Tretyakova, Yu. S., Lavrinenko, S. V., Matveeva, A.A., Martyshev, V.N.
Format:	Journal Article Conference Proceeding
Language:	English
Published:	Les Ulis EDP Sciences 01-01-2015
Subjects:	Conditioning Enriched fuel reactors Flux density Neutron flux Neutrons Nuclear fuel elements Nuclear fuels Thermal neutrons Uranium Uranium dioxide
Online Access:	Get full text
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Summary:	Having analyzed the results obtained in the work, it is possible to conclude that the flux density of fast and thermal neutrons in the shell of fuel elements in EFA in REU-zone decreased on average by 5% for UO2 fuel and by 7% for U9%Mo fuel. Change of neutrons flux density during the cycle does not exceed 4% for both fuel types. On average the fuel burnup in reactor core during the cycle for UO2 and U9%Mo increased by 2.8%. It is 1% less that in HEU-zone, which is conditioned by higher initial loading of 235U in fuel assembly with REU fuel.
ISSN:	2261-236X 2274-7214 2261-236X
DOI:	10.1051/matecconf/20153701059