کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
1570012 | 1514268 | 2006 | 6 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Fabrication method and thermal conductivity assessment of molybdenum-precipitated uranium dioxide pellets
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موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
انرژی هسته ای و مهندسی
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چکیده انگلیسی
UO2 pellets containing molybdenum networks were fabricated when UO2 pellets mixed with 3 or 5 wt% MoO3 powder were sintered in the CO2/CO ratio of 19/1 and then annealed in an H2 atmosphere. The thermal diffusivities of UO2 and Mo-precipitated UO2 pellets were measured in the range of 298–1673 K by a laser flash method and their thermal conductivities were calculated from the thermal diffusivity, the sample density and the published specific heat capacity data. The temperature dependency of the thermal conductivity up to 1673 K in UO2 and Mo-precipitated UO2 was found to be modeled well using the conductivity equation, κ = (A + BT)−1. The thermal conductivity of the Mo-precipitated UO2 was higher than that of the pure UO2.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Journal of Nuclear Materials - Volume 352, Issues 1–3, 30 June 2006, Pages 151–156
Journal: Journal of Nuclear Materials - Volume 352, Issues 1–3, 30 June 2006, Pages 151–156
نویسندگان
Si-Hyung Kim, Chang-Young Joung, Han-Soo Kim, Young-Woo Lee, Ho-Jin Ryu, Dong-Seong Sohn, Dong-Joo Kim,