Work Item
ASTM WK46601

New Test Method for The Determination of the Oxygen to Metal (O/M) Ratio in Sintered Mixed Oxides ((U, Pu)O2) Pellets by Gravimetry

1. Scope

To develop consensus standards for, and promote commercialization of, nuclear fuel cycle, materials, products and processes. The Committee will provide internationally accepted standards which facilitate the commerce; worker safety; public and environemental health; and regulatory compliance within the Nuclear Fuel Cycle. All aspects of the nuclear fuel cycle are included with emphasis on nuclear fuel and reactor materials processing, analysis, and disposal/disposition technolgies and applications. Nuclear fuel cycle activites of both the commercial nuclear industry and the defense community fall within the scope of this committee.

The work of the Committee will be coordinated with other ASTM International committees and national and international organizations having mutual interest.


plutonium; thermal analysis; gravimetry; uranium; MOX; oxygen to metal (O/M) ratio


This standard is needed because it is a method used in large scale MOX fuel fabrication facilities. It will be used to measure O/M ratio in MOX fuel fabricated in the MOX fuel fabrication facility on the Savannah River Site.

The title and scope are in draft form and are under development within this ASTM Committee.


Developed by Subcommittee: C26.05

Committee: C26

Staff Manager: Stephen Mawn

Work Item Status

Date Initiated: 06-30-2014

Technical Contact: Ben Karmiol

Item: 002

Ballot: C26.05 (14-03)

Status: Negative Votes Need Resolution

Item: 015

Ballot: C26 (15-01)

Status: Ballot Item Approved