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Homepage>CSN Standards>40 NUCLEAR ENGINEERING>4040 Nomenclature. Methods of measuring and testing of radioactive products>CSN EN ISO 22765 - Nuclear fuel technology - Sintered (U,Pu)O2 pellets - Guidance for ceramographic preparation for microstructure examination
Released: 01.12.2019
CSN EN ISO 22765 - Nuclear fuel technology - Sintered (U,Pu)O2 pellets - Guidance for ceramographic preparation for microstructure examination

CSN EN ISO 22765

Nuclear fuel technology - Sintered (U,Pu)O2 pellets - Guidance for ceramographic preparation for microstructure examination

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Number of Standard:CSN EN ISO 22765
Category:404046
Pages:20
Released:01.12.2019
Catalog number:508396
DESCRIPTION

CSN EN ISO 22765

CSN EN ISO 22765 This document 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. 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.
Original English text of CSN EN Standard.
The price of the Standard included all amendments and correcturs.