ASTM C1462-21

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Designation: C1462 − 00 (Reapproved 2013) C1462 − 21
Standard Specification for
Uranium Metal Enriched to More than 15 % and Less Than
235 1
20 % U
This standard is issued under the fixed designation C1462; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope
1.1 This specification covers nuclear grade uranium metal that has either 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 U concentration mass
fraction below 20 % (and greater than 15 %) and that is intended for research reactor and generation IV nuclear reactor fuel
fabrication. The scope of this specification includes specifications for enriched uranium metal derived from commercial natural
uranium, recoveredreprocessed uranium, or highly enriched uranium. Commercial natural uranium, recoveredreprocessed uranium
and highly enriched uranium are defined in Section 3. The objectives of this specification are to define the impurity and uranium
isotope limits for commercial grade enriched uranium metal.
1.2 This specification is intended to provide the nuclear industry with a standard for enriched uranium metal which is to be used
in the production of research reactor and generation IV nuclear reactor fuel. 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 standard does not relieve the user of the obligation to
conform to all applicable international, federal, state, and local regulations for processing, shipping, or any other way of using
uranium metal (see, for example, C996 regarding references).
1.4 The values stated in SI units are to be regarded as standard. The values given in parentheses after SI units are provided for
information only and are not considered standard.
1.5 This international standard was developed in accordance with internationally recognized principles on standardization
established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued
by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
2. Referenced Documents
2.1 ASTM Standards:
C696 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide
Powders and Pellets
This specification is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel and Fertile
Material Specifications.
Current edition approved Jan. 1, 2013Oct. 1, 2021. Published January 2013November 2021. Originally approved in 2000. Last previous edition approved in 20082013
as C1462 – 00 (2008).(2013). DOI: 10.1520/C1462-00R13.10.1520/C1462-21.
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
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C1462 − 21
C799 Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-
Grade Uranyl Nitrate Solutions
C859 Terminology Relating to Nuclear Materials
C996 Specification for Uranium Hexafluoride Enriched to Less Than 5 % U
C1233 Practice for Determining Equivalent Boron Contents of Nuclear Materials
C1295 Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium Hexafluoride and Uranyl Nitrate
Solution
C1347 Practice for Preparation and Dissolution of Uranium Materials for Analysis
2.2 ANSI Standard
ANSI-ASME NQA-1 Quality Assurance Program Requirements for Nuclear Facility Applications
2.3 U.S. Government Documents
Code of Federal Regulations, Title 10, Part 50, (Appendix B)
3. Terminology
3.1 Definitions of Terms Specific to This Standard:
3.1.1 Definitions of Terms Specific to This Standard—Terms Terms shall be defined in accordance with Terminology C859, except
for the following:
3.1.2 commercial grade enriched uranium metal—metal, n—uranium metal derived from commercial natural uranium,
recoveredreprocessed uranium, or uranium obtained from the blending of highly enriched uranium with commercial natural
uranium, recoveredreprocessed uranium, or depleted uranium.
3.1.3 commercial natural uranium—uranium, n—any form of natural unirradiated uranium (containing 0.711 +0.711 g 6 0.004
g U per 100 g 100 g U).
3.1.4 depleted uranium—uranium, n—any form of unirradiated uranium with a U content mass fraction less than commercial
natural uranium.
3.1.5 highly enriched uranium—uranium, n—any form of uranium having a U content mass fraction equal to or in excess of
20 %.
3.1.6 recovered uranium—reprocessed uranium, n—any form of uranium that has been exposed in a neutron irradiation facility
and either has been subsequently chemically separated from the fission products and transuranic isotopes so generated, or may be
used as is, due to low irradiation levels.
3.1.6.1 Discussion—
The requirements for recoveredreprocessed uranium are intended to be typical of reprocessed spent fuel from research reactors that
have achieved burn-up levels of up to 50 % of the originally contained fissile material or may have been utilized in critical
facilities. It is recognized that different limits would be necessary to accommodate different fuel histories.
3.1.7 For enriched uranium metal transactions, “buyer” usually represents the research reactor operator or the fuel fabricator, and
“seller” usually represents the supplier of the enriched uranium metal.
4. Health Physics Requirements
4.1 For commercia
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