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
Link To Document :
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