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现行 ISO 22765:2016
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Nuclear fuel technology — Sintered (U,Pu)O2 pellets — Guidance for ceramographic preparation for microstructure examination 核燃料技术 - 烧结(U Pu)O2颗粒 - 陶瓷制备用于显微组织检查的指导
发布日期: 2016-12-05
ISO 22765:2016描述了用于制备烧结(U,Pu)O2颗粒的陶瓷成像程序,用于定性和定量检查颗粒微观结构。 在热处理或化学蚀刻之前和之后进行检查。 他们允许 -观察任何裂纹、晶内和晶间孔隙或夹杂物,以及 -晶粒尺寸、孔隙率和钚均匀性分布的测量。 平均晶粒直径通过经典方法之一测量:计数(截距法)、与标准网格或典型图像的比较等。[2]单个晶粒尺寸的测量需要整个样品上微观结构的均匀发展。 通常通过自动图像分析系统分析钚簇和孔隙的分布和定位。钚分布通常通过化学蚀刻揭示,但也可以使用α-放射自显影术。第一种技术避免了放射自显影术由于α粒子远离源的距离而夸大富钚团簇尺寸的趋势。
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 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.
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归口单位: ISO/TC 85/SC 5
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