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Influence of iron corrosion on nuclear glass alteration processes: nanoscale investigations of the iron-containing phases

机译:铁腐蚀对核玻璃蚀变过程的影响:含铁相的纳米尺度研究

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Several strategies propose to confine High Level Radioactive Waste in a deep geological disposal. Andra (French National Radioactive Waste Management Agency) suggests a multi barrier system including the glass canister, a carbon steel overpack and a low permeability clay host rock to prevent borosilicate glass alteration and to limit migration of radionuclides released under the action of water. However after thousand years and resaturation of clay, water will corrode the carbon steel overpack causing the release of iron ions and precipitation of iron carbonates as corrosion products. The glass matrix will alter through glass hydrolysis and release silicon in solution. Thus, neoformed Fe-Si-O phases can precipitate in the glass alteration layer (GAL) or at the outer part of the GAL and lower the concentration of Si in solution, increasing glass dissolution. Consequently identification and characterization of nanocrystallized Fe-Si-O phases is crucial for modelling the mechanism of glass alteration in contact with iron. The results presented here are obtained on samples (mix of nuclear glass and iron powder) altered in the Underground Research Laboratory of Bure (France). Micro and Nanoscale investigations (Transmission Electron Microscopy, Scanning Transmission X-Ray Microscopy, nanoAuger electron spectroscopy) show presence of neoformed nanocristallized phases (iron silicates) inside GAL and in the iron corrosion products (ICP). Several families of structured Si-Fe-O phases are identified (e.g. smectite in 1CP, chlorite and iron sulfide in GAL) according to the localization and the valence of iron in CP. Moreveor study of the provenance of silicon and iron found in phyllosilicates was carried out in mass spectroscopy (TOF-SIMS). Thereby it is possible to know the proportion of silicon and iron arising from the glass, initially substituted for 29-silicon and 57-iron, to form these silicates.
机译:提出了几种策略来将高放废物限制在深部地质处置中。法国国家放射性废物管理局的安德拉(Andra)建议采用多屏障系统,包括玻璃罐,碳钢外包装和低渗透性粘土基质岩石,以防止硼硅酸盐玻璃发生变化并限制在水作用下释放的放射性核素的迁移。然而,经过数千年的粘土再饱和,水会腐蚀碳钢外包装,导致铁离子的释放和作为腐蚀产物的碳酸铁的沉淀。玻璃基质将通过玻璃水解而发生变化,并在溶液中释放出硅。因此,新形成的Fe-Si-O相可在玻璃蚀变层(GAL)或GAL外部沉淀,并降低溶液中Si的浓度,从而增加玻璃的溶解度。因此,纳米晶Fe-Si-O相的鉴定和表征对于模拟与铁接触的玻璃蚀变机理至关重要。此处显示的结果是在布尔(法国)的地下研究实验室更改过的样品(核玻璃和铁粉的混合物)上获得的。微观和纳米级研究(透射电子显微镜,扫描透射X射线显微镜,nanoAuger电子光谱)显示GAL内部和铁腐蚀产物(ICP)中存在新形成的纳米晶相(硅酸铁)。根据CP中铁的位置和价态,确定了几类结构化的Si-Fe-O相(例如1CP中的蒙脱石,GAL​​中的亚氯酸盐和硫化铁)。在质谱(TOF-SIMS)中对页硅酸盐中发现的硅和铁的来源进行了进一步的研究。因此,有可能知道从玻璃中产生的硅和铁的比例,这些玻璃最初取代了29硅和57铁,从而形成了这些硅酸盐。

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