Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
9793609 | Journal of Nuclear Materials | 2005 | 7 Pages |
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 (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.
Related Topics
Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
F. Clarens, J. de Pablo, I. Casas, J. Giménez, M. Rovira, J. Merino, E. Cera, J. Bruno, J. Quiñones, A. MartÃnez-Esparza,