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Corrosion and dissolution studies of UO2 containing alpha-emitters

机译:含UO2的α发射体的腐蚀和溶解研究

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Corrosion and dissolution of UO2 doped with short-lived alpha-emitters, the so called alpha-doped UO2, was investigated in leaching experiments combined with X-ray Photoelectron Spectroscopy (XPS) analyses. These experiments are part of an ongoing set of tests aiming at evaluating the effects of alpha-radiolysis on the dissolution of the UO2 spent fuel matrix when it will become exposed to groundwater in a deep final repository. Pellets Of UO2 containing similar to 10 and similar to 0.1 wt. % Pu-238 were used. These compositions simulate the alpha-radiation field of different types of commercial LWR spent fuel after different storage times. Undoped UO2 pellets were also used as reference. Static sequential leaching experiments in demineralised water at room temperature under anoxic conditions confirmed that higher fractions of uranium are released in the case of alpha-doped materials compared with undoped UO2. Relatively large amounts of plutonium were found in the leachate of the materials doped with Pu-238. Significant contributions to the total amount released of uranium were found in the rinse solutions of the leaching vessels. The evolution of the U(VI)/U(IV) ratio on the leached surfaces as a function of contact time was studied by deconvolution of the 4f(7/2) uranium peak obtained from the XPS spectra. In the case of undoped UO2, after similar to 1000 h of leaching the increase of the U(VI)/U(IV) ratio stabilized to a level corresponding to similar to UO2.33. The XPS results for both alpha-doped materials showed a continuing increase of the U(VI) fraction on the surface with increasing leaching times after the first similar to 10 h. The rate of increase depended on the alpha-activity of the fuel sample, hence on the amount of radiolysis in the water. After similar to 1000h of leaching, essentially only U(VI) was detected on the surface of the high activity alpha-doped UO2. The presence of a yellowish layer of reprecipitated U(VI) phases covering the surface could be observed optically already after similar to 100 h of leaching. [References: 20]
机译:在与X射线光电子能谱(XPS)分析相结合的浸出实验中,研究了掺杂有短寿命α-发射体的UO2的腐蚀和溶解。这些实验是正在进行的一组测试的一部分,这些测试旨在评估当UO2乏燃料基质将暴露于深层最终储存库中的地下水时对UO2乏燃料基质溶解的影响。 UO2球粒,含有约10 wt。%和约0.1 wt。使用%Pu-238。这些成分在不同的存储时间后,模拟了不同类型的商用轻水堆乏燃料的α辐射场。未掺杂的UO2颗粒也用作参考。在室温,缺氧条件下在软化水中进行的静态连续浸出实验证实,与未掺杂的UO2相比,α掺杂的材料释放出更高比例的铀。在掺入Pu-238的材料的浸出液中发现了相对大量的p。在浸出容器的冲洗溶液中发现了对铀释放总量的重要贡献。通过对从XPS光谱获得的4f(7/2)铀峰进行去卷积研究了浸出表面上U(VI)/ U(IV)比随接触时间的变化。在未掺杂UO2的情况下,经过类似的1000小时浸出后,U(VI)/ U(IV)比的增加稳定在相当于UO2.33的水平。两种α掺杂材料的XPS结果均显示,表面上的U(VI)分数随着第一次类似于10 h的浸出时间的增加而持续增加。增加的速度取决于燃料样品的α活性,因此取决于水中的放射分解量。经过类似于1000h的浸提,在高活性α掺杂的UO2的表面上基本上只检测到U(VI)。经过约100小时的浸提后,已经可以通过光学观察到覆盖表面的再沉淀U(VI)相的微黄色层的存在。 [参考:20]

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