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Mechanistic and kinetic investigation of crystalline UO(2) dissolution.

机译:结晶UO(2)溶解的力学和动力学研究。

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To evaluate the efficacy of REDOX permeable reactive barriers for remediation of uranium contaminated groundwater, knowledge of the fundamental reaction kinetics associated with the dissolution of reduced uranium(IV) dioxide is necessary. Once, oxidizing conditions prevail within the treatment zone uranium can be remobilized. Therefore, the fundamental hypothesis of this dissertation is that under oxic conditions, an oxidative dissolution process controls the remobilization of UO2. The objective is to elucidate the rates of reaction and propose the mechanism(s) associated with this oxidative dissolution process.; Over four decades of existing UO2 dissolution studies, focusing on spent nuclear fuel disposal, have generated numerous inconsistencies and unanswered questions. A cardinal gap in the published literature is the relationship between the activity of carbonate and pH on UO2 (cr) dissolution, as well as the controlling mechanism of dissolution. To resolve these inconsistencies, several UO2 dissolution experiments have been conducted under oxic conditions in the presence of total dissolved carbonate ([CO3 −2]T) from 0.001 to 0.1 M; pH from 7.5 to 10.7; flow rates (q) from 6 to 120 mL d−1: B.E.T. surface area (S) of 1.2 m2 g−1; and temperatures (T) from 25° to 90°C utilizing both powder and pellet specimens in a single pass flow-through apparatus.; Steady state conditions were achieved in each experiment after approximately seven reactor volumes. The elemental release rate of uranium from the UO 2 specimen increases by an order of magnitude with each 30-degree increase in temperature. Measured log10 rates (mol m−2 s−1) at 30° and 60°C at a flow rate of 120 mL d−1 for the powder specimens were −9.84 ± 0.08 and −8.88 ± 0.05, respectively. Additionally, these results show that UO2 dissolution rate varies as a function of the ratio of flow rate, q, to sample surface area, S, which indicates reaction affinity control. At values of log10 q/S greater than −9.2, UO 2 dissolution becomes invariant with respect to q/S, which is evidence for dissolution at the forward rate of reaction. Other factors that affect the rate of dissolution include [CO3−2 ]T, pH, and carbonate activity {lcub}CO32− {rcub}.; From the results of these experiments at 30°C the following rate equations were derived, where [] and {lcub}{rcub} denotes the concentration (in molar) and activity (in molar) of a particular species in solution, respectively.; cwl="83:114" wdm="100"> row> cell>(0.001 M [CO3−2]T 0.1 M) cell>Log10 Rate = 0.7375 Log10 [CO3 −2]T − 6.78 row rht="0.00px"> cell>(7.5 pH 9.7) cell>Log10 Rate = 0.2720 Log10 [H+] − 12.01 row> cell>(0.0003 M {lcub}CO32−{rcub} 0.03 M) cell>Log10 Rate = 0.3023 Log10 {lcub}CO3 −2{rcub} −8.92 row rht="0.00px"> cell spn="2"> (Abstract shortened by UMI.)
机译:为了评估REDOX渗透性反应性屏障对铀污染地下水的修复作用,必须了解与溶解还原的二氧化铀有关的基本反应动力学。一旦在处理区内普遍存在氧化条件,就可以将铀转移出去。因此,本文的基本假设是在有氧条件下,氧化溶解过程控制着UO 2 的迁移。目的是阐明反应速率并提出与该氧化溶解过程有关的机理。现有四十多年的UO 2 溶出度研究集中在乏核燃料处置上,产生了许多不一致之处和未解决的问题。公开文献中的一个主要空白是碳酸盐活性和pH对UO 2 (cr)溶解的关系,以及溶解的控制机制。为了解决这些矛盾,已经在有氧条件下在总溶解碳酸盐([CO 3 -2 )存在的条件下进行了一些UO 2 溶解实验。 ] T )从0.001到0.1 M; pH从7.5至10.7;流量(q)从6到120 mL d -1 :B.E.T.表面积(S)为1.2 m 2 g −1 ;在单程流通设备中使用粉末和颗粒样品,温度(T)为25°至90°C;在约7个反应堆体积后,每个实验均达到稳态条件。温度每升高30度,UO 2 标本中铀的元素释放速率就会增加一个数量级。在30°C和60°C下以120 mL d <的流量测得的log 10 速率(mol m -2 s -1 )粉末样品的super> -1 分别为-9.84±0.08和-8.88±0.05。此外,这些结果表明,UO 2 的溶解速率随流速q与样品表面积S的比值的变化而变化,这表明反应亲和力得到了控制。当log 10 q / S值大于-9.2时,UO 2 溶出度相对于q / S不变,这是在正向反应速率下溶出度的证据。影响溶解速率的其他因素包括[CO 3 −2 ] T ,pH和碳酸盐活性{lcub} CO 3 2-− {rcub}。从30℃下这些实验的结果,得出以下速率方程,其中[]和{lcub} {rcub}分别表示溶液中特定物质的浓度(摩尔)和活性(摩尔)。 cwl =“ 83:114” wdm =“ 100”> row> cell>(0.001 M <[CO 3 −2 ] T <0.1 M) cell> Log 10 速率= 0.7375 Log 10 [CO 3 -2 ] T -6.78 row rht =“ 0.00px”> cell>(7.5 H <9.7) cell> Log 10 速率= 0.2720 Log 10 [H + ] − 12.01 row> cell>(0.0003 M <{lcub} CO 3 2- {rcub} <0.03 M) cell> Log 10 速率= 0.3023 Log 10 {lcub} CO < sub> 3 −2 {rcub} −8.92 row rht =“ 0.00px“> cell spn =” 2“>(摘要由U缩短MI。)

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