http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
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 한국원자력학회 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 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%.
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%.