Comparative Analysis of Structural Changes in U-Mo Dispersed Fuel of Full-size Fuel Elements and Mini-rods Irradiated in the MIR Reactor

Aleksey L. Izhutov; Valeriy V. Iakovlev; Andrey E. Novoselov; Vladimir A. Starkov; Aleksey A. Sheldyakov; Valeriy Yu Shiishin; Vladimir M. Kosenkov; Aleksandr V. Vatulin; Irina V. Dobrikova; Vladimir B. Suprun; Gennadiy V. Kulakov

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자료유형: 학술저널

저자정보: Aleksey L. Izhutov Valeriy V. Iakovlev Andrey E. Novoselov Vladimir A. Starkov Aleksey A. Sheldyakov Valeriy Yu Shiishin Vladimir M. Kosenkov Aleksandr V. Vatulin Irina V. Dobrikova Vladimir B. Suprun Gennadiy V. Kulakov

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제45권 제7호

발행연도: 2013.1

수록면: 859 - 870 (12page)

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The paper summarizes the irradiation test and post-irradiation examination (PIE) data for the U-Mo low-enriched fuel thatwas irradiated in the MIR reactor under the RERTR Program. The PIE data were analyzed for both full-size fuel rods andmini-rods with atomized powder dispersed in Al matrix as well as with additions of 2%, 5% and 13% of silicon in the matrixand ZrN protective coating on the fuel particles. The full-size fuel rods were irradiated up to an average burnup of ~ 60%235U; the mini-rods were irradiated to an averageburnup of ~ 85%235U. The presented data show a significant increase of the void fraction in the U-Mo alloy as the U-235burnup rises from ~ 40% up to ~ 85%. The effect of irradiation test conditions and U-235 burnup were analyzed with regard tothe 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%.

#U-Mo Fuel #Al Matrix #Si Additions #ZrN Coating #High Burnup #Scanning Electron Microscopy #SEM) #Electron Probe Microanalysis #EPMA)

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