کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
1566725 1514227 2011 23 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Thermodynamic modelling of advanced oxide and carbide nuclear fuels: Description of the U-Pu-O-C systems
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی انرژی هسته ای و مهندسی
پیش نمایش صفحه اول مقاله
Thermodynamic modelling of advanced oxide and carbide nuclear fuels: Description of the U-Pu-O-C systems
چکیده انگلیسی
► A thermodynamic modelling of the U-Pu-O-C system is derived using the CALPHAD method. ► The calculated phase diagrams of all the sub-systems and the thermodynamic properties of all the phases are described and found in good agreement with the experimental data. ► The variation of the oxygen potential in oxide fuels versus oxygen to metal ratio is explained by the change of the cation oxidation states and the formation of oxygen vacancies and interstitials.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Journal of Nuclear Materials - Volume 419, Issues 1–3, December 2011, Pages 145-167
نویسندگان
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