Title of article :
Thermal conductivity evaluation of high burnup mixed-oxide (MOX) fuel pellet
Author/Authors :
Amaya، نويسنده , , Masaki and Nakamura، نويسنده , , Jinichi and Nagase، نويسنده , , Fumihisa and Fuketa، نويسنده , , Toyoshi، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2011
Pages :
6
From page :
303
To page :
308
Abstract :
The thermal conductivity formula of fuel pellet which contains the effects of burnup and plutonium (Pu) addition was proposed based on the Klemens’ theory and reported thermal conductivities of unirradiated (U, Pu) O2 and irradiated UO2 pellets. The thermal conductivity of high burnup MOX pellet was formulated by applying a summation rule between phonon scattering parameters which show the effects of plutonium addition and burnup. Temperature of high burnup MOX fuel was evaluated based on the thermal conductivity integral which was calculated from the above-mentioned thermal conductivity formula. Calculated fuel temperatures were plotted against the linear heat rates of the fuel rods, and were compared with the fuel temperatures measured in a test reactor. Since both values agreed well, it was confirmed that the proposed thermal conductivity formula of MOX pellets is adequate.
Journal title :
Journal of Nuclear Materials
Serial Year :
2011
Journal title :
Journal of Nuclear Materials
Record number :
1362579
Link To Document :
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