IRT Research Reactor Burnup Calculation for the Analysis of Conversion to Low Enrichment Uranium Fuel

7/14/2012 2012 - #03 Fuel cycle and nuclear waste management

Ivakhin S.V. Radaev A.I. Tikhomirov G.V. Shchurovskaya M.V.

https://doi.org/10.26583/npe.2012.3.11

Neutronic characteristics of IRT-3M fuel assembly with dioxide high enrichment uranium (HEU) fuel and uranium-molybdenum low enrichment uranium (LEU) fuel are considered. Results of calculation of irradiated fuel isotope composition are presented. Test problems for IRT cells with HEU and LEU fuel calculated by MCU and MCNP codes are proposed.

Link for citing the article: Ivakhin S.V., Radaev A.I., Tikhomirov G.V., Shchurovskaya M.V. IRT Research Reactor Burnup Calculation for the Analysis of Conversion to Low Enrichment Uranium Fuel. Izvestiya vuzov. Yadernaya Energetika. 2012, no. 3, pp. 81-90; DOI: https://doi.org/10.26583/npe.2012.3.11 (in Russian).