1.1 This specification covers nuclear grade uranium
hexafluoride (UF6) that either has been processed through an
enrichment plant, or has been produced by the blending of
Highly Enriched Uranium with other uranium to obtain uranium
of any 235U concentration from 5 % to less than 20 % and that is intended
for fuel fabrication. The objectives of this specification are
twofold: (1) To define the impurity and uranium isotope limits
for Enriched Commercial Grade UF6 so that, with respect to
fuel design and manufacture, it is essentially equivalent to
enriched uranium made from natural UF6; and (2) To define
limits for Enriched Reprocessed UF6 to be expected if Reprocessed
UF6 is to be enriched without dilution with Commercial
Natural UF6. For such UF6, special provisions, not defined
herein, may be needed to ensure fuel performance and to
protect the work force, process equipment, and the environment.
1.2 This specification is intended to provide the nuclear
industry with a standard for enriched UF6 that is to be used in
the production of uranium compounts for fuel fabrication.
In addition to this specification, the parties concerned may
agree to other appropriate conditions.
1.3 The scope of this specification does not comprehensively
cover all provisions for preventing criticality accidents
or requirements for health and safety or for shipping. Observance
of this specification does not relieve the user of the
obligation to conform to all applicable international, federal,
state, and local regulations for processing, shipping, or in any
other way using UF6 (see, for example, TID-7016, DP-532, and
The proposed new fleet of Advanced Gas Reactors uses significantly higher enrichment levels of uranium to operate. Also some blending of Highly Enriched Uranium (HEU) stock may supply temporary supplies, ultimately new uranium needs to be enriched for the HALEU market, ostensibly from commercial natural uranium sources or existing Low Enriched Uranium (LEU) stock from ASTM C996 compliant stock. Users include HTGC reactors using TRISO ceramic fuels and some molten salt reactors.
The title and scope are in draft form and are under development within this ASTM Committee.
Developed by Subcommittee: C26.02
Staff Manager: Stephen Mawn
Date Initiated: 05-10-2022
Technical Contact: Stephen Poirier