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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%.
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%.
Prolongation of the BOR-60 reactor operation
ALEXEY L. IZHUTOV,YURI M. KRASHENINNIKOV,IGOR Y. ZHEMKOV,ARTEM V. VARIVTSEV,YURI V. NABOISHCHIKOV,VICTOR S. NEUSTROEV,VALENTIN K. SHAMARDIN 한국원자력학회 2015 Nuclear Engineering and Technology Vol.47 No.3
The fast neutron reactor BOR-60 is one of the key experimental facilities worldwide to perform large-scale tests of fuel, absorbing, and structural materials for advanced reactors. The BOR-60 reactor was put into operation in December 1969, and by the end of 2014 it had been operating on power for ∼265,000 hours. BOR-60 still demonstrates potential capabilities to extend the lifetime of sodium-cooled fast reactors. The BOR-60 lifetime should have expired at the end of 2014. Over the past few years, a great scope of work has been performed to justify the possibility of extending its lifetime. The work included inspection of the equipment conditions, calculations and experimental research on operating parameters and the conditions of nonremovable components, investigation of the structural material samples after their long-term operation under irradiation, etc. Based on the results of the work performed, the residual lifetime was evaluated and the reactor operator made a decision to extend the lifetime period of the BOR-60 reactor. After considering both a set of documents about the reactor conditions and the positive decision of independent experts, the Regulatory Authority of the Russian Federation extended the BOR-60 operating license up to 2020.