کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
1569624 999929 2006 11 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Simulations of heat and oxygen diffusion in UO2 nuclear fuel rods
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی انرژی هسته ای و مهندسی
پیش نمایش صفحه اول مقاله
Simulations of heat and oxygen diffusion in UO2 nuclear fuel rods
چکیده انگلیسی

We present finite-element simulations of coupled heat and oxygen atom diffusion for UO2 fuel pellets. The expressions for thermal conductivity, specific heat and oxygen diffusivity for the fuel element are obtained directly from previously published correlations, or from analysis of previously published data. We examine the temperature and non-stoichiometry distributions for a varying range of conditions. Simulations are performed for steady-state and transient regime in one-dimensional (purely radial) configurations. For steady-state conditions we perform parametric studies that determine the maximum temperature in the fuel rod as a function of non-stoichiometry and heat generation rate intensity. For transient simulations, we examine the time lag in the response of the temperature and non-stoichiometry distributions with respect to sudden changes in heat generation rate intensity and oxygen removal rate. All simulations are performed with the commercial code COMSOL Multiphysics™.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Journal of Nuclear Materials - Volume 359, Issue 3, 15 December 2006, Pages 174–184
نویسندگان
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