ASTM C1334-05e1

Standard Specification for Uranium Oxides with a ²³⁵U Content of Less Than 5 % for Dissolution Prior to Conversion to Nuclear-Grade Uranium Dioxide

SCOPE
1.1 This specification covers uranium oxides, including processed byproducts or scrap material (powder, pellets, or pieces), that are intended for dissolution into uranyl nitrate solution meeting the requirements of Specification C 788 prior to conversion into nuclear grade UO2 powder with a  235U content of less than 5 %. This specification defines the impurity and uranium isotope limits for such urania powders that are to be dissolved prior to processing to nuclear grade UO2 as defined in Specification C 753.
1.2 This specification provides the nuclear industry with a general standard for such uranium oxide powders. It recognizes the diversity of conversion processes and the processes to which such powders are subsequently to be subjected (for instance, by solvent extraction). It is therefore anticipated that it may be necessary to include supplementary specification limits by agreement between the buyer and seller.
1.3 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents, for health and safety, or for shipping. Observance of this specification does not relieve the user of the obligation to conform to all international, national, state and local regulations for processing, shipping, or any other way of using urania powders (see 2.2 and 2.3).

General Information

• Status: Historical
• Publication Date: 31-Dec-2004
• ICS: 27.120.30 - Fissile materials and nuclear fuel technology
• Technical Committee: C26 - Nuclear Fuel Cycle
• Drafting Committee: C26.02 - Fuel and Fertile Material Specifications

Relations

• Replaces: ASTM C1334-05 - Standard Specification for Uranium Oxides with a ²³⁵U Content of Less Than 5 % for Dissolution Prior to Conversion to Nuclear-Grade Uranium Dioxide
• Effective Date: 01-Jan-2005
• Replaced By: ASTM C1334-05(2010) - Standard Specification for Uranium Oxides with a ²³⁵U Content of Less Than 5 % for Dissolution Prior to Conversion to Nuclear-Grade Uranium Dioxide
• Effective Date: 01-Mar-2010
• Referred By: ASTM C1413-18 - Standard Test Method for Isotopic Analysis of Hydrolyzed Uranium Hexafluoride and Uranyl Nitrate Solutions by Thermal Ionization Mass Spectrometry
• Effective Date: 01-Jan-2005

Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information.
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Designation: C1334 – 05
Standard Specification for
235
Uranium Oxides with a U Content of Less Than 5 % for
Dissolution Prior to Conversion to Nuclear-Grade Uranium
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Dioxide
This standard is issued under the fixed designation C1334; 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.
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´ NOTE—Editorial changes were made in June 2006.
1. Scope C696 Test Methods for Chemical, Mass Spectrometric, and
Spectrochemical Analysis of Nuclear-Grade Uranium Di-
1.1 This specification covers uranium oxides, including
oxide Powders and Pellets
processed byproducts or scrap material (powder, pellets, or
C753 Specification for Nuclear-Grade, Sinterable Uranium
pieces), that are intended for dissolution into uranyl nitrate
Dioxide Powder
solution meeting the requirements of Specification C788 prior
235
C788 Specification for Nuclear-Grade Uranyl Nitrate Solu-
to conversion into nuclear grade UO powder with a U
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tion or Crystals
contentoflessthan5 %.Thisspecificationdefinestheimpurity
C799 Test Methods for Chemical, Mass Spectrometric,
and uranium isotope limits for such urania powders that are to
Spectrochemical, Nuclear, and Radiochemical Analysis of
be dissolved prior to processing to nuclear grade UO as
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Nuclear-Grade Uranyl Nitrate Solutions
defined in Specification C753.
C859 Terminology Relating to Nuclear Materials
1.2 This specification provides the nuclear industry with a
C996 Specification for Uranium Hexafluoride Enriched to
generalstandardforsuchuraniumoxidepowders.Itrecognizes
235
Less Than 5 % U
the diversity of conversion processes and the processes to
C1233 Practice for Determining Equivalent Boron Contents
which such powders are subsequently to be subjected (for
of Nuclear Materials
instance, by solvent extraction). It is therefore anticipated that
E105 Practice for Probability Sampling Of Materials
it may be necessary to include supplementary specification
2.2 ANSI Standard:
limits by agreement between the buyer and seller.
ANSI/ASME NQA-1 Quality Assurance Requirements for
1.3 The scope of this specification does not comprehen-
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Nuclear Facility Applications
sively cover all provisions for preventing criticality accidents,
2.3 U.S. Government Document:
for health and safety, or for shipping. Observance of this
Federal Regulations Title 10, (Energy) Part 50, Domestic
specification does not relieve the user of the obligation to
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Licensing of Production and Utilization Facilities
conform to all international, national, state and local regula-
tionsforprocessing,shipping,oranyotherwayofusingurania
3. Terminology
powders (see 2.2 and 2.3).
3.1 Definition of Term Specific to This Standard:
2. Referenced Documents 3.1.1 Terms shall be defined in accordance with Terminol-
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ogy C859, except for the following:
2.1 ASTM Standards:
3.1.2 Commercial Grade Uranium Oxide, n—any oxide of
uranium made from unirradiated uranium. It is recognized
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This specification is under the jurisdiction of ASTM Committee C26 on
some contamination with reprocessed uranium may occur
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel
and Fertile Material Specifications.
Current edition approved Jan. 1, 2005. Published February 2005. Originally
approved in 1996. Last previous edition approved in 2000 as C1334 – 96 (2000).
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DOI: 10.1520/C1334-05E01. Withdrawn.
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For referenced ASTM standards, visit the ASTM website, www.astm.org, or Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM 4th Floor, New York, NY 10036.
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Standards volume information, refer to the standard’s Document Summary page on AvailablefromU.S.GovernmentPrintingOfficeSuperintendentofDocuments,
the ASTM website. 732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
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C1334 – 05
during routine processing; this is acceptable provided that the waived provided the seller can characterize the material, for
specification for Commercial Grade Uranium Oxide as set example, through the seller’s QA records.
forth in 4.1 is met.
5.3 Equivalent Boron Content—The total equivalent boron
3.1.3 scrap, n—inthenuclearindustry,residuesthatcontain
content (EBC) shall not exceed 2.0 µg/gU.The list of elements
sufficient quantities of source or special nuclear material to be
to be considered in the EBC calculation shall be as recom-
worthy of recovery.
mended in Practice C1233. The me
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