کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
9781827 1511637 2005 6 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Separation and recovery study of uranium from spent NaF (fillers)
موضوعات مرتبط
مهندسی و علوم پایه مهندسی مواد مواد الکترونیکی، نوری و مغناطیسی
پیش نمایش صفحه اول مقاله
Separation and recovery study of uranium from spent NaF (fillers)
چکیده انگلیسی
The molten salt technique is considered to be a feasible technique applicable for the removal of uranium from the spent NaF (fillers). Simple spent NaF or NaF with NaCl, i.e. mixed salt, was used as an electrolyte and the uranium concentrations in the bath, pre-treatment condition, electrolytic temperature, current density, etc. were given as parameters in this experiment. Results from the fundamental experiments showed the potential applicability of the molten salt technique for the removal of uranium from spent NaF.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Journal of Physics and Chemistry of Solids - Volume 66, Issues 2–4, February–April 2005, Pages 602-607
نویسندگان
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