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DIN EN ISO 22765:2024-01

DIN EN ISO 22765:2024-01

Nuclear fuel technology - Sintered (U,Pu)O<(Index)2> pellets - Guidance for ceramographic preparation for microstructure examination (ISO/DIS 22765:2023); English version prEN ISO 22765:2023 / Note: Date of issue 2023-12-15*Intended as replacement for DIN EN ISO 22765 (2019-11).

Technologie du combustible nucléaire - Pastilles (U,Pu)O<(Index)2> frittées - Préconisations relatives à la préparation céramographique pour examen de la microstructure (ISO/DIS 22765:2023); Version anglaise prEN ISO 22765:2023 / Attention: Date de parution 2023-12-15*Prévu pour remplacer DIN EN ISO 22765 (2019-11).

Kernbrennstofftechnologie - Gesinterte (U,Pu)O<(Index)2>-Pellets - Leitfaden für die keramographische Herstellung der Proben zur Untersuchung des Feingefüges (ISO/DIS 22765:2023); Englische Fassung prEN ISO 22765:2023 / Achtung: Erscheinungsdatum 2023-12-15*Vorgesehen als Ersatz für DIN EN ISO 22765 (2019-11).

Date:
2024-01 /Active
Idiomas Disponibles:
Inglés
International equivalences:

prEN ISO 22765 (2023-12)

ISO/DIS 22765 (2023-12)

Summary:
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.
Keywords:
Ceramography, Design, Dies (press tools), Dimensions, Etching, Fatigue testing, Flaws, Grain size, Granulates, Guide books, Homogeneity, Identification methods, Image analysis, Inclusions, Investigations, Metals, Microstructure, Nuclear energy, Nuclear fuels, Pellets, Plutonium, Pores, Porosity, Powder metallurgy, Production, Radius, Sintered, Sintered products, Stress concentration, Test specimens
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