ASTM C1462-21
(Specification)Standard Specification for Uranium Metal Enriched to Less Than 20 % 235U
Standard Specification for Uranium Metal Enriched to Less Than 20 % <sup> 235</sup >U
ABSTRACT
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 235U concentration below 20 % (and greater than 15 %) and that is intended for research reactor fuel fabrication. The uranium content of commercial grade enriched uranium metal shall be greater than or equal to 99.85 weight percent. The isotopic requirements for enriched uranium metal are presented in details. The chemical and isotopic composition shall be tested to meet the requirements prescribed.
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 235U mass fraction below 20 % 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, reprocessed uranium, or highly enriched uranium. Commercial natural uranium, reprocessed 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.
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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.
Designation:C1462 −21
Standard Specification for
235 1
Uranium Metal Enriched to Less Than 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 2. Referenced Documents
2
1.1 This specification covers nuclear grade uranium metal 2.1 ASTM Standards:
that has either been processed through an enrichment plant, or
C696 Test Methods for Chemical, Mass Spectrometric, and
has been produced by the blending of highly enriched uranium
Spectrochemical Analysis of Nuclear-Grade Uranium Di-
235
with other uranium, to obtain uranium of any U mass
oxide Powders and Pellets
fraction below 20 % and that is intended for research reactor
C799 Test Methods for Chemical, Mass Spectrometric,
andgenerationIVnuclearreactorfuelfabrication.Thescopeof
Spectrochemical, Nuclear, and RadiochemicalAnalysis of
this specification includes specifications for enriched uranium
Nuclear-Grade Uranyl Nitrate Solutions
metal derived from commercial natural uranium, reprocessed
C859 Terminology Relating to Nuclear Materials
uranium, or highly enriched uranium. Commercial natural
C996 Specification for Uranium Hexafluoride Enriched to
235
uranium,reprocesseduraniumandhighlyenricheduraniumare
Less Than 5 % U
defined in Section 3. The objectives of this specification are to
C1233 Practice for Determining Equivalent Boron Contents
define the impurity and uranium isotope limits for commercial
of Nuclear Materials
grade enriched uranium metal.
C1295 Test Method for Gamma Energy Emission from
Fission and Decay Products in Uranium Hexafluoride and
1.2 This specification is intended to provide the nuclear
Uranyl Nitrate Solution
industrywithastandardforenricheduraniummetalwhichisto
C1347 Practice for Preparation and Dissolution of Uranium
be used in the production of research reactor and generation IV
Materials for Analysis
nuclear reactor fuel. In addition to this specification, the parties
3
concerned may agree to other appropriate conditions. 2.2 ANSI Standard
ANSI-ASME NQA-1 Quality Assurance Program Require-
1.3 The scope of this specification does not comprehen-
ments for Nuclear Facility Applications
sively cover all provisions for preventing criticality accidents
4
or requirements for health and safety or for shipping. Obser-
2.3 U.S. Government Documents
vance of this standard does not relieve the user of the
CodeofFederalRegulations, Title10,Part50,(AppendixB)
obligation to conform to all applicable international, federal,
state, and local regulations for processing, shipping, or any
3. Terminology
other way of using uranium metal (see, for example, C996
3.1 Definitions of Terms Specific to This Standard:
regarding references).
3.1.1 Terms shall be defined in accordance with Terminol-
1.4 The values stated in SI units are to be regarded as
ogy C859, except for the following:
standard. The values given in parentheses after SI units are
3.1.2 commercial grade enriched uranium metal,
provided for information only and are not considered standard.
n—uranium metal derived from commercial natural uranium,
1.5 This international standard was developed in accor-
reprocesseduranium,oruraniumobtainedfromtheblendingof
dance with internationally recognized principles on standard- highly enriched uranium with commercial natural uranium,
ization established in the Decision on Principles for the
reprocessed uranium, or depleted uranium.
Development of International Standards, Guides and Recom-
mendations issued by the World Trade Organization Technical
Barriers to Trade (TBT) Committee.
2
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
1
This specification is under the jurisdiction of ASTM Committee C26 on the ASTM website.
3
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
and Fertile Material Specifications. 4th Floor, New York, NY 10036, http://www.ansi.org.
4
Current edition approved Oct. 1, 2021. Published November 2021. Originally AvailablefromU.S.GovernmentPrintingOfficeSuperintendentofDocuments,
approved in 2000. Last previous edition approved in 2013 as C1462 – 00 (2013). 732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, http://
DOI: 10.1520/C1462
...
This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
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
235
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
2.1 ASTM Standards:
C696 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide
Powders and Pellets
1
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.
2
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.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
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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
235
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
3
2.2 ANSI Standard
ANSI-ASME NQA-1 Quality Assurance Program Requirements for Nuclear Facility Applications
4
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
...
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