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QUANTIFICATION BY EPMA OF GLASS FOR NUCLEAR APPLICATION

机译:EPMA对核应用玻璃的定量

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摘要

The confinement of high-level radioactive waste from spent nuclear fuel reprocessing is a key issue in the nuclear fuel cycle. In France, the waste storage strategy is based on four containment barriers including, respectively, a glass matrix for radioactive waste immobilisation, a primary stainless steel canister, a thick carbon steel overpack and finally a host rock. Substantial research is carried out on nuclear glass to improve the properties of the confinement material. Depending on the glass composition and process parameters crystals can appear in the glass matrix. The characterisation of these phases (micrometre size) and of the glass matrix surrounding them is of great importance for a proper understanding of the glass properties and its long term performance. The composition of these phases can be characterised by means of electron microprobe (CAMECA SX100) with a standard resolution electron beam. In order to improve the quantification of such small dimension inclusions, the use of a FEG-EPMA CAMECA SXFiveFE, which is well adapted to micrometre-range analysis, has been tested to determine their chemical composition. The improved analytical resolution obtained with the FEG-EPMA made it possible to optimise the analysis of the micro particles, and to determine their chemical composition. The nature of the crystal phases was confirmed by electron backscatter diffraction (EBSD) analysis coupled with SEM and confirmed the crystalline phases of apatite and cerianite measured by EPMA. To study the glass matrix near the crystals in a more precise way, thin lamellas were prepared by focussed FIB ion beam milling. A microstructural analysis by TEM was performed to characterise the glass matrix and the inclusions and their chemical composition was determined by EDS quantification. These thin lamella were also analysed by EPMA in transmission with the CAMECA SX 100 to get a more complete analysis of elements, including especially some light elements such as boron. TEM-EDS and EPMA analyses confirm a peculiar Zr enrichment in the glass matrix just around the inclusions.
机译:将乏核燃料后处理中的高放废物加以限制是核燃料循环中的关键问题。在法国,废物存储策略基于四个遏制屏障,分别是用于固定放射性废物的玻璃基质,主要的不锈钢罐,厚的碳钢外包装以及最后的主体岩石。在核玻璃上进行了大量研究以改善限制材料的性能。根据玻璃的成分和工艺参数,晶体会出现在玻璃基质中。这些相(微米级)和围绕它们的玻璃基质的表征对于正确理解玻璃性能及其长期性能非常重要。这些相的组成可以通过带有标准分辨率电子束的电子探针(CAMECA SX100)来表征。为了改进此类小尺寸夹杂物的定量,已经测试了非常适合微米范围分析的FEG-EPMA CAMECA SXFiveFE的使用,以确定它们的化学成分。用FEG-EPMA获得的更高的分析分辨率使得优化微粒分析和确定其化学成分成为可能。晶相的性质通过结合SEM的电子背散射衍射(EBSD)分析得到确认,并通过EPMA证实了磷灰石和陶粒的晶相。为了更精确地研究晶体附近的玻璃基体,通过聚焦FIB离子束研磨制备了薄薄片。通过TEM进行了微结构分析,以表征玻璃基体和内含物及其化学组成,并通过EDS定量测定。 EPMA还与CAMECA SX 100一起对这些薄层进行了分析,以对元素进行更完整的分析,尤其是某些轻元素,例如硼。 TEM-EDS和EPMA分析证实,夹杂物周围的玻璃基质中Zr富集。

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