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Izhutov, Aleksey.L.,Iakovlev, Valeriy.V.,Novoselov, Andrey.E.,Starkov, Vladimir.A.,Sheldyakov, Aleksey.A.,Shishin, Valeriy.Yu.,Kosenkov, Vladimir.M.,Vatulin, Aleksandr.V.,Dobrikova, Irina.V.,Suprun, V Korean Nuclear Society 2013 Nuclear Engineering and Technology Vol.45 No.7
The paper summarizes the irradiation test and post-irradiation examination (PIE) data for the U-Mo low-enriched fuel that was irradiated in the MIR reactor under the RERTR Program. The PIE data were analyzed for both full-size fuel rods and mini-rods with atomized powder dispersed in Al matrix as well as with additions of 2%, 5% and 13% of silicon in the matrix and ZrN protective coating on the fuel particles. The full-size fuel rods were irradiated up to an average burnup of ${\sim}60%^{235}U$; the mini-rods were irradiated to an average burnup of ${\sim}85%^{235}U$. The presented data show a significant increase of the void fraction in the U-Mo alloy as the U-235 burnup rises from ~ 40% up to ~ 85%. The effect of irradiation test conditions and U-235 burnup were analyzed with regard to the formation of an interaction layer between the matrix and fuel particles as well as generation of porosity in the U-Mo alloy. Shown here are changes in distribution of U fission products as the U-235 burnup increases from ~ 40% up to ~ 85%.