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首页> 外文期刊>Radiochimica Acta: International Journal for Chemical Aspects of Nuclear Science and Technology >Oxidation and dissolution rates of UO2(s) in carbonate-rich solutions under external alpha irradiation and initially reducing conditions
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Oxidation and dissolution rates of UO2(s) in carbonate-rich solutions under external alpha irradiation and initially reducing conditions

机译:在外部α辐射和初始还原条件下,UO2在富含碳酸盐的溶液中的氧化和溶解速率

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This paper describes the effects of aqueous carbonate concentrations on the UO2 oxidation and dissolution rates under an alpha beam irradiation in a cyclotron. As solid samples, UO2 colloids were synthesized by nano-particle precipitation. The specific surface area obtained is 85.3 m(2)/g. All aqueous solutions were buffered in the pH range 8 < pH < 9. The observation of particles under TEM and X-ray diffraction showed well-crystallized UO2. Molecular radiolysis products such as H2O2 and carbonate degradation products where analysed. Solution analysis of dissolved uranium and of radiolytically generated H2O2 allowed to deduce dissolution rates of UO2 as well as H2O2 consumption rates (deduced from the H2O2 concentrations in presence of UO2 colloids and those in irradiated blank solutions). In absence of carbonate, the dissolution rates of UO2 are much lower than the H2O2 consumption rates. The difference is explained by the oxidation of uranium(IV) at the UO2/solution interface (e.g. formation of U3O7). In contrast, in the presence of carbonate (up to 4 x 10(-2) mol/L), the dissolution rates of UO2 are similar to H2O2 consumption rates. In this case the oxidized uranium is complexed with carbonate ions resulting in highly soluble species as indicated by the geochemical model PHREEQC calculations [UO2(CO3)(3)(4-)]. The high carbonate concentration did not affect the H2O2 formation/consumption rates. Radiolytic decomposition of carbonate ions and formation of organic radiolytic degradation products were negligible. The results indicate that under the present experimental conditions, UO2 oxidation by H2O2 and UO2 dissolution are connected as a sequential reaction: for a given H2O2 concentration, UO2 oxidation occurs at a constant rate. At low carbonate concentration, the dissolution of oxidized UO2 is slower than the oxidation rate (hence oxidation is not rate limiting), while at high carbonate concentrations all oxidized UO2 becomes immediately dissolved and UO2 oxidation becomes rate limiting for UO2 dissolution. This mechanism is in agreement with that proposed in the Matrix Alteration Model (MAM).
机译:本文描述了回旋加速器中α束辐照下碳酸盐水溶液浓度对UO2氧化和溶解速率的影响。作为固体样品,通过纳米颗粒沉淀法合成了UO2胶体。获得的比表面积为85.3 m(2)/ g。所有水溶液都在8 H <9的pH范围内缓冲。在TEM和X射线衍射下观察到的颗粒显示出良好结晶的UO2。分析了分子放射分解产物,例如H2O2和碳酸盐降解产物。溶解铀和辐射分解生成的H2O2的溶液分析可以推断出UO2的溶解速率以及H2O2的消耗速率(由存在UO2胶体和辐照空白溶液中的H2O2浓度推导)。在没有碳酸盐的情况下,UO2的溶解速率远低于H2O2的消耗速率。区别在于铀(IV)在UO2 /溶液界面的氧化(例如形成U3O7)。相反,在存在碳酸盐(最高4 x 10(-2)mol / L)的情况下,UO2的溶解速率类似于H2O2的消耗速率。在这种情况下,如地球化学模型PHREEQC计算[UO2(CO3)(3)(4-)]所示,氧化铀与碳酸根离子络合形成高度可溶的物质。高碳酸盐浓度不会影响H2O2的形成/消耗速率。碳酸根离子的辐射分解和有机辐射降解产物的形成可以忽略不计。结果表明,在当前的实验条件下,H2O2引起的UO2氧化和UO2的溶解是一个顺序反应:对于给定的H2O2浓度,UO2氧化以恒定速率发生。在低碳酸盐浓度下,氧化的UO2的溶解比氧化速率慢(因此氧化不受速率限制),而在高碳酸盐浓度下,所有氧化的UO2立即溶解,而UO2氧化成为限制UO2溶解的速率。该机制与矩阵变更模型(MAM)中提出的机制一致。

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