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现行 BS EN ISO 22765:2019
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Nuclear fuel technology. Sintered (U,Pu)O<sub>2</sub> pellets. Guidance for ceramographic preparation for microstructure examination 核燃料技术 烧结(U Pu)O<sub>2</sub> 显微结构检查用陶瓷制备指南
发布日期: 2019-06-21
本文件描述了用于制备烧结(U,Pu)O2颗粒的陶瓷工艺,用于颗粒微观结构的定性和定量检查。 检查在热处理或化学蚀刻前后进行。 它们允许——观察任何裂纹、晶内和晶间孔隙或夹杂物,以及——测量粒度、孔隙度和钚均匀性分布。 平均晶粒直径通过经典方法之一进行测量:计数(截距法)、与标准网格或典型图像进行比较等[2]单个晶粒尺寸的测量要求整个试样的微观结构均匀发展。 钚团簇、孔隙分布和定位通常由自动图像分析系统进行分析。钚的分布通常通过化学蚀刻显示,但也可以使用α放射自显影。 第一种技术避免了放射自显影由于α粒子离开源的距离而夸大富钚团簇大小的趋势。交叉引用:ISO 3696ASTM E112包含以下内容:勘误表,2019年6月
This document describes the ceramographic procedure used to prepare sintered (U,Pu)O2pellets for qualitative and quantitative examination of the pellet microstructure. The examinations are performed before and after thermal treatment or chemical etching. They allow— observation of any cracks, intra- and intergranular pores or inclusions, and— measurement of the grain size, porosity and plutonium homogeneity distribution. The mean grain diameter is measured by one of the classic methods: counting (intercept method), comparison with standard grids or typical images, etc.[2]The measurement of individual grain sizes requires uniform development of the microstructure over the entire specimen. The plutonium cluster and pore distribution and localization are generally analysed by automatic image analysis systems. The plutonium distribution is usually revealed by chemical etching but alpha-autoradiography can also be used. The first technique avoids the tendency for autoradiography to exaggerate the size of plutonium-rich clusters due to the distance the alpha particles travel away from the source.Cross References:ISO 3696ASTM E112Incorporates the following:Corrigendum, June 2019
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发布单位或类别: 英国-英国标准学会
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