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The structural role of Zr within alkali borosilicate glasses for nuclear waste immobilisation

机译:Zr在碱性硼硅酸盐玻璃中用于固定核废料的结构作用

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摘要

Zirconium is a key constituent element of High Level nuclear Waste (HLW) glasses, occurring both as a fission product and a fuel cladding component. As part of a wider research program aimed at optimising the solubility of zirconium in HLW glasses, we have investigated the structural chemistry of zirconium in such materials using X-ray Absorption Spectroscopy (XAS). Zirconium K-edge XAS data were acquired from several inactive simulant and simplified waste glass compositions, including a specimen of blended Magnox/UO_2 fuel waste glass. These data demonstrate that zirconium is immobilised as (octahedral) six-fold coordinate ZrO_6 species in these glasses, with a Zr-O contact distance of 2.09 ?. The next nearest neighbours of the Zr species are Si at 3.42 ? and possibly Na at 3.44 ?, no next nearest neighbour Zr could be resolved.
机译:锆是高放核废料(HLW)玻璃的关键组成元素,它既是裂变产物又是燃料包壳成分。作为旨在优化锆在HLW玻璃中的溶解度的更广泛研究计划的一部分,我们使用X射线吸收光谱法(XAS)研究了锆在此类材料中的结构化学。锆K-edge XAS数据是从几种不活跃的模拟和简化废玻璃成分中获得的,包括混合的Magnox / UO_2燃料废玻璃样品。这些数据表明锆在这些玻璃中被固定为(八面体)六倍坐标ZrO_6种类,Zr-O接触距离为2.09Ω。 Zr物种的下一个最近邻居是Si在3.42?如果Na为3.44 ?,则无法解析下一个最近的邻居Zr。

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