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现行 BS ISO 22765:2016
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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: 2016-12-31
BS ISO 22765:2016描述了用于制备烧结(U,Pu)O2颗粒的陶瓷工艺 球团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,并测量粒度、孔隙度和钚均匀性分布。平均粒径通过一种经典方法测量:计数法(截距法), 与标准网格或典型图像等进行比较。 [2] 单个粒度的测量 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分析系统进行分析 图像分析系统。钚的分布通常通过化学蚀刻而非α放射自显影来显示 也可以使用。第一种技术避免了放射自显影术 由于阿尔法粒子离开的距离,夸大了富钚团簇的大小 消息来源。交叉引用:ISO 3696ASTM E112购买本文件时提供的所有当前修订版均包含在购买本文件中。
BS ISO 22765:2016 describes the ceramographic procedure used to prepare sintered (U,Pu)O2 pellets for qualitative and quantitative examination of the pellet microstructure.The examinations are performed before and after thermal treatment or chemical etching.They allowobservation of any cracks, intra- and intergranular pores or inclusions, andmeasurement 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 alphaautoradiography 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 E112All current amendments available at time of purchase are included with the purchase of this document.
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发布单位或类别: 英国-英国标准学会
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