Nuclear fuel technology - Sintered (U,Pu)O2 pellets - Guidance for ceramographic preparation for microstructure examination (ISO/DIS 22765:2023)

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.

Kernbrennstofftechnologie - Gesinterte (U,Pu)O₂-Pellets - Leitfaden für die keramographische Herstellung der Proben zur Untersuchung des Feingefüges (ISO/DIS 22765:2023)

Technologie du combustible nucléaire - Pastilles (U,Pu)O2 frittées - Préconisations relatives à la préparation céramographique pour examen de la microstructure (ISO/DIS 22765:2023)

ISO 18610:2016 décrit la procédure céramographique utilisée pour préparer des pastilles de (U,Pu)O2 frittées afin de réaliser des examens qualitatifs et quantitatifs de leur microstructure.
Ces examens sont réalisés avant et après un traitement thermique ou une attaque chimique.
Ils permettent:
- l'observation d'éventuels fissures, pores inter- et intragranulaires ou inclusions; et
- le mesurage des tailles de grains, de la porosité et de l'homogénéité de la distribution du plutonium.
Le diamètre de grain moyen est mesuré par l'une des méthodes classiques suivantes: comptage (méthode par interception), comparaison à des grilles normalisées ou des images types, etc[2]. Le mesurage des dimensions du grain requiert la révélation uniforme de la microstructure sur l'ensemble de l'échantillon.
La localisation et la distribution des pores et des agglomérats de plutonium sont en général analysées par des systèmes automatiques d'analyse des images. La distribution du plutonium est, en règle générale, mise en évidence par une attaque chimique mais il est également possible d'utiliser l'autoradiographie alpha. La première technique évite la tendance propre à l'autoradiographie, d'exagérer la taille des agglomérats riches en plutonium en raison de la distance parcourue par les particules alpha depuis la source.

Tehnologija jedrskih goriv - Sintrani peleti (U, Pu)O2 - Navodilo za pripravo keramografske preiskave mikrostrukture (ISO/DIS 22765:2023)

General Information

Status
Not Published
Publication Date
14-Jul-2025
Current Stage
4060 - Closure of enquiry - Enquiry
Start Date
12-Mar-2024
Completion Date
12-Mar-2024

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SLOVENSKI STANDARD
oSIST prEN ISO 22765:2024
01-februar-2024
Tehnologija jedrskih goriv - Sintrani peleti (U, Pu)O2 - Navodilo za pripravo
keramografske preiskave mikrostrukture (ISO/DIS 22765:2023)
Nuclear fuel technology - Sintered (U,Pu)O2 pellets - Guidance for ceramographic
preparation for microstructure examination (ISO/DIS 22765:2023)
Kernbrennstofftechnologie - Gesinterte (U,Pu)O¿-Pellets - Leitfaden für die
keramographische Herstellung der Proben zur Untersuchung des Feingefüges (ISO/DIS
22765:2023)
Technologie du combustible nucléaire - Pastilles (U,Pu)O2 frittées - Préconisations
relatives à la préparation céramographique pour examen de la microstructure (ISO/DIS
22765:2023)
Ta slovenski standard je istoveten z: prEN ISO 22765
ICS:
27.120.30 Cepljivi materiali in jedrska Fissile materials and nuclear
gorivna tehnologija fuel technology
oSIST prEN ISO 22765:2024 en,fr,de
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.

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oSIST prEN ISO 22765:2024

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oSIST prEN ISO 22765:2024
DRAFT INTERNATIONAL STANDARD
ISO/DIS 22765
ISO/TC 85/SC 5 Secretariat: BSI
Voting begins on: Voting terminates on:
2023-12-19 2024-03-12
Nuclear fuel technology — Sintered (U,Pu)O2 pellets
— Guidance for ceramographic preparation for
microstructure examination
Technologie du combustible nucléaire — Pastilles (U,Pu)O2 frittées — Préconisations relatives à la
préparation céramographique pour examen de la microstructure
ICS: 27.120.30
This document is circulated as received from the committee secretariat.
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oSIST prEN ISO 22765:2024
ISO/DIS 22765:2023(E)
DRAFT INTERNATIONAL STANDARD
ISO/DIS 22765
ISO/TC 85/SC 5 Secretariat: BSI
Voting begins on: Voting terminates on:

Nuclear fuel technology — Sintered (U,Pu)O2 pellets
— Guidance for ceramographic preparation for
microstructure examination
Technologie du combustible nucléaire — Pastilles (U,Pu)O2 frittées — Préconisations relatives à la
préparation céramographique pour examen de la microstructure
ICS: 27.120.30
This document is circulated as received from the committee secretariat.
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PROVIDE SUPPORTING DOCUMENTATION. © ISO 2023

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oSIST prEN ISO 22765:2024
ISO/DIS 22765:2023(E)
Contents Page
Foreword .iv
1 Scope .
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