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A kinetic study of UO2 dissolution and H2O2 stability in the presence of groundwater ions

机译:地下水离子存在下UO2溶解和H2O2稳定性的动力学研究

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Current reactors spent nuclear UO2 fuel, that will probably enter geologic formations for disposal, is assumed to get into contact with groundwater of a repository earliest after several thousands of years. After this time, its alpha activity will be still high enough to induce a process of water radiolysis that leads to production of oxidants and, probably, to the oxidative dissolution of the material, that could start a mobilisation of radiotoxic nuclides. The main oxidant produced during this process would be hydrogen peroxide (H2O2), which is thermodynamically unstable and can decompose during reactions with certain groundwater ions. Information on the stability of H2O2 is therefore important for assessing the behaviour of the material in the repository. We investigated the stability of H2O2 and the correlated dissolution of U from UO2 as a function of the concentration of H2O2 and of the groundwater ions carbonate, sulphate, and silicate. Decomposition of H2O2 was measured in the presence and absence Of UO2(cr). We monitored the concentrations of H2O2, U-diss, groundwater ions, O-2 (diss), and the pH in aqueous solution under Ar atmosphere. The lowest stabilities (in average) for H2O2 were found in carbonate solutions. When comparing the effect of carbonate systems containing UO2(cr) to carbonate solutions without a solid phase, we found that in some of the homogeneous tests H2O2 was consumed faster. This effect was not observed with the other groundwater ions. Also, U dissolution rates were significantly lower in the carbonate experiments than in those with sulphate or silicate. The results suggest that a radical-controlled mechanism (similar to the Halpern - Smith-mechanism of dissolved U(IV) oxidation) takes place at the UO2 surface during dissolution. The hypothesis is supported by ESR measurements on hydroxyl radical scavenging by the carbonate ion.
机译:假定目前的反应堆用过的核UO2燃料可能会进入地质地层进行处置,这是在几千年后最早与储存库的地下水接触的。在此时间之后,其α活性仍将足够高,以诱导水的放射分解过程,从而导致氧化剂的产生,并可能导致物质的氧化溶解,从而可能开始动员放射性核素。在此过程中产生的主要氧化剂是过氧化氢(H2O2),它在热力学上是不稳定的,在与某些地下水离子反应时会分解。因此,有关H2O2稳定性的信息对于评估存储库中材料的行为很重要。我们研究了H2O2的稳定性以及UU2从UO2的溶解与H2O2浓度以及地下水离子碳酸盐,硫酸盐和硅酸盐的关系。在有和没有UO2(cr)的情况下测量H2O2的分解。我们在Ar气氛下监测H2O2,U-dis,地下水离子,O-2(diss)的浓度以及水溶液中的pH值。在碳酸盐溶液中,H2O2的稳定性最低(平均)。当比较含UO2(cr)的碳酸盐体系与不含固相的碳酸盐溶液的效果时,我们发现在某些均相测试中,H2O2的消耗更快。其他地下水离子未观察到这种效果。而且,碳酸盐实验中的U溶出速率明显低于硫酸盐或硅酸盐中的U溶出速率。结果表明,在溶解过程中,UO2表面发生了自由基控制的机制(类似于溶解的U(IV)氧化的Halpern-Smith机制)。通过碳酸盐离子清除羟基自由基的ESR测量支持该假设。

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