Abstract

CONTAINED IN VOL. 12.01, 2018 Specifies the procedure for preparing nuclear-grade uranium dioxide (UO2) or mixed uraniumplutonium dioxide (MOX or (U,Pu)O[2])), sintered and nonirradiated pellets for subsequent microstructural analysis (hereafter referred to as ceramographic examination).

General Product Information

Published
Document Type	Standard
Status	Current
Publisher	American Society for Testing and Materials
Pages
ISBN
Committee	C 26