1994
DOI: 10.1557/proc-353-609
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Mechanism of Unirradiated UO2 (S) Dissolution in Nacl and Mgcl2 Brines at 25°C

Abstract: The dissolution of unirradiated U0 2 (s) has been studied in NaCI and MgCI 2 brines under both reducing and oxidizing conditions.The initial uranium release under reducing conditions has been attributed to the dissolution of an initial oxidized layer. The final uranium concentrations have been modeled by using the PHRQPITZ computer program giving the solubility of the solid phase U0 2 (s).Under oxidizing conditions, the initial release is the sum of the oxidized layer dissolution and the oxidation/dissolution … Show more

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Cited by 4 publications
(3 citation statements)
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“…6.0x10" 4.0x10" 6 In the experiments carried out in both reducing and oxidizing conditions, there is an initial increase of the uranium concentration in solution with time. This increase has been attributed to the dissolution of an oxidized layer placed initially on the U0 2 [6] which will be formed even if care is taken during the experimental procedure to keep an oxygen free atmosphere around the solid surface [9,10]. The existence of this oxidized layer on the surface of the solid used in our experiments was proved by means of X-ray photoelectron spectroscopy determinations of the solid surface.…”
Section: Resultsmentioning
confidence: 99%
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“…6.0x10" 4.0x10" 6 In the experiments carried out in both reducing and oxidizing conditions, there is an initial increase of the uranium concentration in solution with time. This increase has been attributed to the dissolution of an oxidized layer placed initially on the U0 2 [6] which will be formed even if care is taken during the experimental procedure to keep an oxygen free atmosphere around the solid surface [9,10]. The existence of this oxidized layer on the surface of the solid used in our experiments was proved by means of X-ray photoelectron spectroscopy determinations of the solid surface.…”
Section: Resultsmentioning
confidence: 99%
“…This decrease is due to the precipitation of U0 2 which it is the thermodynamic stable solid phase at these conditions and the uranium concentration in solution exceeds its solubility. Using the PHRQPITZ code [11], the U0 2 solubility has been calculated to be 3 · 10~7 mol/kg [6] in both brines because the reaction taking place at the experimental pH of both brines during this precipitation step is the following [6]: U(OH) 4 (aq) ο U0 2 (s) + 2 H 2 0 (4) Equation (3) has been fitted to the experimental data. The results obtained are shown in Table 3, and the best fitting of the model to the experimental data can be seen in Fig.…”
Section: Experiments Carried Out Under Reducing Conditionsmentioning
confidence: 99%
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