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Contribution of Energetically Reactive Surface Features to the Dissolution of CeO2 and ThO2 Analogues for Spent Nuclear Fuel Microstructures

机译:活性反应表面特征对废核燃料微结构中CeO2和ThO2类似物溶解的贡献

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In the safety case for the geological disposal of nuclear waste, the release of radioactivity from the repository is controlled by the dissolution of the spent fuel in groundwater. There remain several uncertainties associated with understanding spent fuel dissolution, including the contribution of energetically reactive surface sites to the dissolution rate. In this study, we investigate how surface features influence the dissolution rate of synthetic CeO2 and ThO2, spent nuclear fuel analogues that approximate as closely as possible the microstructure characteristics of fuel-grade UO2 but are not sensitive to changes in oxidation state of the cation. The morphology of grain boundaries (natural features) and surface facets (specimen preparation-induced features) was investigated during dissolution. The effects of surface polishing on dissolution rate were also investigated. We show that preferential dissolution occurs at grain boundaries, resulting in grain boundary decohesion and enhanced dissolution rates. A strong crystallographic control was exerted, with high misorientation angle grain boundaries retreating more rapidly than those with low misorientation angles, which may be due to the accommodation of defects in the grain boundary structure. The data from these simplified analogue systems support the hypothesis that grain boundaries play a role in the so-called "instant release fraction" of spent fuel, and should be carefully considered, in conjunction with other chemical effects, in safety performance assessements for the geological disposal of spent fuel. Surface facets formed during the sample annealing process also exhibited a strong crystallographic control and were found to dissolve rapidly on initial contact with dissolution medium, Defects and strain induced during sample polishing caused an overestimation of the dissolution rate, by up to 3 orders of magnitude.
机译:在核废料地质处置的安全情况下,处置库中放射性的释放是通过将乏燃料溶解在地下水中来控制的。与理解乏燃料的溶解有关,仍然存在一些不确定性,包括能量反应性表面位点对溶解速率的贡献。在这项研究中,我们调查了表面特征如何影响合成CeO2和ThO2的溶解速度,这些废核燃料类似物尽可能接近燃料级UO2的微观结构特征,但对阳离子氧化态的变化不敏感。在溶解过程中研究了晶界(自然特征)和表面刻面(试样制备诱导的特征)的形态。还研究了表面抛光对溶解速率的影响。我们表明优先溶蚀发生在晶界,导致晶界脱粘和提高溶出速率。施加了强大的晶体学控制,高取向角的晶界比低取向角的晶界退缩更快,这可能是由于晶界结构中存在缺陷所致。来自这些简化的模拟系统的数据支持以下假设:晶界在乏燃料的所谓“即时释放分数”中起作用,并且在与地质学的安全性能评估中应结合其他化学效应仔细考虑处理乏燃料。在样品退火过程中形成的表面刻面也表现出很强的晶体学控制,并且发现在与溶解介质初次接触时迅速溶解。样品抛光过程中引起的缺陷和应变导致溶解率高估了3个数量级。

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