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Kinetic and thermodynamic studies of the dissolution of thorium-uranium (IV) phosphate-diphosphate solid solutions

机译:磷酸or铀(IV)-二磷酸固溶体溶解的动力学和热力学研究

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The dissolution of thorium-uranium (IV) phosphate-diphosphate solid solutions (TUPD) was studied as a function of the temperature and leachate acidity. The dependence of the normalized dissolution rate on the temperature leads to an activation energy equal to ab out 40 kJ mol(-1), dose to that obtained for the pure thorium phosphate-diphosphate (42 +/- 3 kJ mol(-1)) and for thorium-plutonium (IV) phosphate-diphosphate solid solutions (41 +/- 1 kJ mol(-1)). The normalized dissolution rate of TUPD slightly increases with the leachate acidity. The partial order related to the proton concentration, n, is equal to 0.40 +/- 0.02 while the apparent normalized dissolution rate constant, k ' (T,I), reaches (2.8 +/- 0.7) x 10(-4) g m(-2) d(-1) at 90 degreesC and for [H3O+] = 1 M. When the saturation of the leachate is reached, the concentration of thorium, uranium and phosphate ions measured in the solution are controlled by the precipitation of the uranyl phosphate pentahydrate (UO2)(3) (PO4)(2). 5H(2)O and the thorium phosphate-hydrogenphosphate Th-2(PO4)(2)(HPO4).H2O. Both solids were extensively characterized using XRD, infrared and UV-visible spectroscopies or electron probe microanalysis (EPMA). Their solubility products, K ' (S,0), were determined and extrapolated to I = 0. They are equal to 10(-55.2 +/-0.5) and 10(-66.6 +/-1.2), respectively. All the samples leached were characterized using EPMA, SEM and TEM. These techniques showed that during the dissolution process, thorium and uranium are completely separated as (UO2)(3)(PO4). 5H(2)O, on one hand, and Th-2(PO4)(2)(HPO4).H2O, on the other hand. In the first days of leaching tests, an amorphous additional phase, identified as Th-2(PO4)(2)(HPO4). nH(2)O was also observed. Several leaching tests performed on sintered TUPD samples revealed that the dissolution rates measured in 10(-1) M HNO3 is very low (6.5 x 10(-5) g d(-1)) by comparison to other ceramics studied in the same objective. In these conditions, the thorium phosphate-diphosphate (TPD) appears as a promising ceramic for the immobilization of tetravalent actinides like uranium, neptunium or plutonium. (C) 2001 Elsevier Science B.V. All rights reserved. [References: 64]
机译:研究了or铀(IV)磷酸盐-二磷酸盐固溶体(TUPD)的溶解度与温度和浸出酸度的关系。归一化溶解速率对温度的依赖性导致活化能约等于40 kJ mol(-1),相当于纯磷酸二氢or(42 +/- 3 kJ mol(-1)的剂量)。 )和磷酸or-IV(IV)-二磷酸solid固溶体(41 +/- 1 kJ mol(-1))。 TUPD的归一化溶解速率随渗滤液酸度的增加而略有增加。与质子浓度相关的偏序n等于0.40 +/- 0.02,而表观归一化溶解速率常数k'(T,I)达到(2.8 +/- 0.7)x 10(-4)gm (-2)在90°C且[H3O +] = 1 M时的d(-1)。当浸出液达到饱和时,溶液中measured,铀和磷酸盐离子的浓度由磷酸铀酰五水合物(UO2)(3)(PO4)(2)。 5H(2)O和磷酸or-磷酸氢Th-2(PO4)(2)(HPO4).H2O。两种固体均使用XRD,红外和紫外可见光谱或电子探针微分析(EPMA)进行了广泛表征。确定了它们的溶解度乘积K'(S,0)并外推至I =0。它们分别等于10(-55.2 +/- 0.5)和10(-66.6 +/- 1.2)。使用EPMA,SEM和TEM对所有浸出的样品进行表征。这些技术表明,在溶解过程中,or和铀被完全分离为(UO2)(3)(PO4)。一方面是5H(2)O,另一方面是Th-2(PO4)(2)(HPO4).H2O。在浸出测试的第一天,无定形的附加相被标识为Th-2(PO4)(2)(HPO4)。还观察到了nH(2)O。在烧结的TUPD样品上进行的几次浸出试验表明,与在同一目标中研究的其他陶瓷相比,在10(-1)M HNO3中测得的溶出度非常低(6.5 x 10(-5)g d(-1))。在这些条件下,磷酸二氢or(TPD)似乎是一种有前途的陶瓷,可用于固定铀,n或p等四价act系元素。 (C)2001 Elsevier Science B.V.保留所有权利。 [参考:64]

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