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

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 C1334-96(2000) - 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 C1334-05e1 - 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
• 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NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.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
Designation: C 1334 – 05
Standard Specification for
235
Uranium Oxides with a U Content of Less Than 5 % for
Dissolution Prior to Conversion to Nuclear-Grade Uranium
1
Dioxide
This standard is issued under the fixed designation C 1334; 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 (e) indicates an editorial change since the last revision or reapproval.
1. Scope C 788 Specification for Nuclear-Grade Uranyl Nitrate So-
lution
1.1 This specification covers uranium oxides, including
C 799 Test Methods for Chemical, Mass Spectrometric,
processed byproducts or scrap material (powder, pellets, or
Spectrochemical, Nuclear, and Radiochemical Analysis of
pieces), that are intended for dissolution into uranyl nitrate
2
Nuclear-Grade Uranyl Nitrate Solutions
solution meeting the requirements of Specification C 788 prior
235
C 859 Terminology Relating to Nuclear Materials
to conversion into nuclear grade UO powder with a U
2
C 996 Specification for Uranium Hexafluoride Enriched to
contentoflessthan5 %.Thisspecificationdefinestheimpurity
235
Less Than 5 % U
and uranium isotope limits for such urania powders that are to
C 1233 Practice for Determining Equivalent Boron Con-
be dissolved prior to processing to nuclear grade UO as
2
tents of Nuclear Materials
defined in Specification C 753.
E 105 Practice for Probability Sampling of Materials
1.2 This specification provides the nuclear industry with a
2.2 ANSI Standard:
generalstandardforsuchuraniumoxidepowders.Itrecognizes
ANSI/ASME NQA-1 Quality Assurance Requirements for
the diversity of conversion processes and the processes to
3
Nuclear Facility Applications
which such powders are subsequently to be subjected (for
2.3 U.S. Government Document:
instance, by solvent extraction). It is therefore anticipated that
Federal Regulations Title 10, (Energy) Part 50, Domestic
it may be necessary to include supplementary specification
4
Licensing of Production and Utilization Facilities
limits by agreement between the buyer and seller.
1.3 The scope of this specification does not comprehen-
3. Terminology
sively cover all provisions for preventing criticality accidents,
3.1 Definition of Term Specific to This Standard:
for health and safety, or for shipping. Observance of this
3.1.1 Terms shall be defined in accordance with Terminol-
specification does not relieve the user of the obligation to
ogy C 859, except for the following:
conform to all international, national, state and local regula-
3.1.2 Commercial Grade Uranium Oxide, n—any oxide of
tionsforprocessing,shipping,oranyotherwayofusingurania
uranium made from unirradiated uranium. It is recognized
powders (see 2.2 and 2.3).
some contamination with reprocessed uranium may occur
2. Referenced Documents during routine processing; this is acceptable provided that the
2
specification for Commercial Grade Uranium Oxide as set
2.1 ASTM Standards:
forth in 4.1 is met.
C 696 Test Methods for Chemical, Mass Spectrometric, and
3.1.3 scrap, n—inthenuclearindustry,residuesthatcontain
Spectrochemical Analysis of Nuclear-Grade Uranium Di-
sufficient quantities of source or special nuclear material to be
oxide Powders and Pellets
worthy of recovery.
C 753 Specification for Nuclear-Grade, Sinterable Uranium
Dioxide Powder
4. Isotopic Content
4.1 For Commercial Grade Uranium Oxide with an isotopic
1 235
This specification is under the jurisdiction of ASTM Committee C26 on
content of U between that of natural uranium and 5 %, the
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel
isotopic and radionuclide limits of Specification C 996 shall
and Fertile Material Specifications.
Current edition approved Jan. 1, 2005. Published February 2005. Originally
approved in 1996. Last previous edition approved in 2000 as C 1334 – 96 (2000).
2 3
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.
4
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.
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C1334–05
apply. The specific isotopic and radionuclide measurements 5.5 Moisture Content—Themoisturecontentoftheuranium
required by Specification C 996 may be waived, provided that oxide shall not exceed 1 % by weight un
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