Title of article
The oxidative dissolution of unirradiated UO2 by hydrogen peroxide as a function of pH
Author/Authors
Clarens، نويسنده , , F. and de Pablo، نويسنده , , J. and Casas، نويسنده , , I. and Giménez، نويسنده , , J. and Rovira، نويسنده , , M. and Merino، نويسنده , , J. and Cera، نويسنده , , E. and Bruno، نويسنده , , J. and Quiٌones، نويسنده , , J. and Martيnez-Esparza، نويسنده , , A.، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2005
Pages
7
From page
225
To page
231
Abstract
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 (10−5 mol dm−3), the UO2 dissolution rate decreases linearly with pH while at alkaline pH the dissolution rate increases linearly with pH. At higher H2O2 concentrations (10−3 mol dm−3) the dissolution rates are lower than the ones at 10−5 mol dm−3 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 × 10−7– 5 × 10−5 mol dm−3 according to our results, which is in agreement with H2O2 concentrations determined in spent fuel leaching experiments.
Journal title
Journal of Nuclear Materials
Serial Year
2005
Journal title
Journal of Nuclear Materials
Record number
1362900
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