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DIN EN ISO 16793:2021-04

DIN EN ISO 16793:2021-04

Nuclear fuel technology - Guidelines for ceramographic preparation of UO<(Index)2> sintered pellets for microstructure examination (ISO 16793:2018); English version EN ISO 16793:2021

Technologie du combustible nucléaire - Lignes directrices pour la préparation céramographique de pastilles UO<(Index)2> frittées pour l'examen de la microstructure (ISO 16793:2018); Version anglaise EN ISO 16793:2021

Kernbrennstofftechnologie - Leitfaden für die keramographische Herstellung gesinterter UO<(Index)2>-Pellets zur Untersuchung des Feingefüges (ISO 16793:2018); Englische Fassung EN ISO 16793:2021

Date:
2021-04 /Active
Idiomas Disponibles:
Inglés
International equivalences:

EN ISO 16793:2021

ISO 16793:2018

Relación con otras normas DIN:
Summary:
This document describes the ceramographic preparation of uranium dioxide (UO2) sintered pellets for qualitative and quantitative microstructure examinations.These examinations can be carried out before and after thermal or chemical etching.They enable- observations of fissures, inter- or intra-granular pores and inclusions, and- measurement of pore and grain size and measurement of pore and grain size distributions.The measurement of average grain size can be carried out using a classical counting method as described in ISO 2624 or ASTM E112[3], i.e. intercept procedure, comparison with standard grids or reference photographs.The measurement of pore-size distributions is usually carried out by an automatic image analyser. If the grain-size distributions are also measured with an image analyser, it is recommended that thermal etching be used to reveal the grain structure uniformly throughout the whole sample.
Keywords:
Ceramography, Etching, Guide books, Investigations, Materials testing, Methods of analysis, Microstructure, Nuclear energy, Nuclear fuels, Nuclear technology, Particle size distribution, Particle size measurement, Pellets, Production, Radiation protection, Radioactive materials, Sample preparation, Sintered, Sintered products, Specimen preparation, Structure, Uranium dioxide, Uranium dioxide pellets, Uranium oxide, Uranium-containing
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