کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
9793609 | 1514275 | 2005 | 7 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
The oxidative dissolution of unirradiated UO2 by hydrogen peroxide as a function of pH
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موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
انرژی هسته ای و مهندسی
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چکیده انگلیسی
The dissolution of non-irradiated UO2 was studied as a function of both pH and hydrogen peroxide concentration (simulating radiolytic generated product). At acidic pH and a relatively low hydrogen peroxide concentration (10â5 mol dmâ3), the UO2 dissolution rate decreases linearly with pH while at alkaline pH the dissolution rate increases linearly with pH. At higher H2O2 concentrations (10â3 mol dmâ3) the dissolution rates are lower than the ones at 10â5 mol dmâ3 H2O2, which has been attributed to the precipitation at these conditions of studtite (UO4 · 4H2O, which was identified by X-ray diffraction), together with the possibility of hydrogen peroxide decomposition. In the literature, spent fuel dissolution rates determined in the absence of carbonate fall in the H2O2 concentration range 5 Ã 10â7- 5 Ã 10â5 mol dmâ3 according to our results, which is in agreement with H2O2 concentrations determined in spent fuel leaching experiments.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Journal of Nuclear Materials - Volume 345, Issues 2â3, 15 October 2005, Pages 225-231
Journal: Journal of Nuclear Materials - Volume 345, Issues 2â3, 15 October 2005, Pages 225-231
نویسندگان
F. Clarens, J. de Pablo, I. Casas, J. Giménez, M. Rovira, J. Merino, E. Cera, J. Bruno, J. Quiñones, A. MartÃnez-Esparza,