Standard Practice for Ceramographic Preparation of UO2 and Mixed Oxide (U,Pu)O2 Pellets for Microstructural Analysis

Importancia y uso:

5.1 The ceramographic examination of the nuclear fuel pellet is mandatory to ensure that the microstructural characteristics are in compliance with the fuel specifications relative to performance in reactor, particularly concerning thermo-mechanical behavior and fission gas release.

5.2 This practice is applicable for sintered UO₂ pellets with any ²³⁵U concentration and (U,Pu)O₂ pellets containing up to 15 weight % PuO₂ with less than 10 % porosity.

Subcomité:

C26.05

Volúmen:

12.01

Número ICS:

27.120.30 (Fissile materials and nuclear fuel technology)

Palabras clave:

ceramographic examination; chemical etching; microstructural analysis; microstructure; MOX; thermal etching; (U,Pu)O2; UO2;