Standard Specification for Uranium Oxides with a <sup>235</sup>U 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 C788 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 C753.  
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).  
1.4 Units—The values stated in SI units are to be regarded as standard. No other units of measurement are included in this 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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ASTM C1334-05(2022) - Standard Specification for Uranium Oxides with a <sup>235</sup>U Content of Less Than 5 % for Dissolution Prior to Conversion to Nuclear-Grade Uranium Dioxide
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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:C1334 −05 (Reapproved 2022)
Standard Specification for
Uranium Oxides with a U Content of Less Than 5% for
Dissolution Prior to Conversion to Nuclear-Grade Uranium
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.
1. Scope 2. Referenced Documents
1.1 This specification covers uranium oxides, including 2.1 ASTM Standards:
processed byproducts or scrap material (powder, pellets, or C696 Test Methods for Chemical, Mass Spectrometric, and
pieces), that are intended for dissolution into uranyl nitrate Spectrochemical Analysis of Nuclear-Grade Uranium Di-
solution meeting the requirements of Specification C788 prior oxide Powders and Pellets
to conversion into nuclear grade UO powder with a U C753 Specification for Nuclear-Grade, Sinterable Uranium
contentoflessthan5 %.Thisspecificationdefinestheimpurity Dioxide Powder
and uranium isotope limits for such urania powders that are to C788 Specification for Nuclear-Grade Uranyl Nitrate Solu-
be dissolved prior to processing to nuclear grade UO as tion or Crystals
defined in Specification C753. C799 Test Methods for Chemical, Mass Spectrometric,
Spectrochemical, Nuclear, and RadiochemicalAnalysis of
1.2 This specification provides the nuclear industry with a
Nuclear-Grade Uranyl Nitrate Solutions
generalstandardforsuchuraniumoxidepowders.Itrecognizes
C859 Terminology Relating to Nuclear Materials
the diversity of conversion processes and the processes to
C996 Specification for Uranium Hexafluoride Enriched to
which such powders are subsequently to be subjected (for
Less Than 5 % U
instance, by solvent extraction). It is therefore anticipated that
C1233 Practice for Determining Equivalent Boron Contents
it may be necessary to include supplementary specification
of Nuclear Materials
limits by agreement between the buyer and seller.
E105 Guide for Probability Sampling of Materials
1.3 The scope of this specification does not comprehen-
2.2 ASME Standard:
sively cover all provisions for preventing criticality accidents,
ASME NQA-1 QualityAssurance Requirements for Nuclear
for health and safety, or for shipping. Observance of this
Facility Applications
specification does not relieve the user of the obligation to
2.3 U.S. Government Document:
conform to all international, national, state and local regula-
Federal Regulations Title 10, (Energy) Part 50, Domestic
tionsforprocessing,shipping,oranyotherwayofusingurania
Licensing of Production and Utilization Facilities
powders (see 2.2 and 2.3).
1.4 Units—The values stated in SI units are to be regarded
3. Terminology
as standard. No other units of measurement are included in this
3.1 Definitions of Terms Specific to This Standard:
standard.
3.1.1 Terms shall be defined in accordance with Terminol-
1.5 This international standard was developed in accor-
ogy C859, except for the following:
dance with internationally recognized principles on standard-
3.1.2 Commercial Grade Uranium Oxide, n—any oxide of
ization established in the Decision on Principles for the
uranium made from unirradiated uranium. It is recognized
Development of International Standards, Guides and Recom-
mendations issued by the World Trade Organization Technical
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Barriers to Trade (TBT) Committee.
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.
1 3
This specification is under the jurisdiction of ASTM Committee C26 on Available from American Society of Mechanical Engineers (ASME), ASME
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel International Headquarters, Two Park Ave., New York, NY 10016-5990, http://
and Fertile Material Specifications. www.asme.org.
Current edition approved July 1, 2022. Published July 2022. Originally approved AvailablefromU.S.GovernmentPrintingOfficeSuperintendentofDocuments,
ɛ1
in 1996. Last previous edition approved in 2016 as C1334 – 05 (2016) . DOI: 732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, http://
10.1520/C1334-05R22. www.access.gpo.gov.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
C1334−05 (2022)
some contamination with reprocessed uranium may occur and toxic elements such asAg, Cr, Pb, Hg, Se, Sb, andAs shall
during routine processing; this is acceptable provided that the be reported for information. Analysis requirements may be
specification for Commercial Grade Uranium Oxide as set waived provided the seller can characterize the material, for
forth in 4.1 is met. example, through the seller’s QA records.
3.1.3 scrap, n—in the nuclear industry, residues that contain
5.3 Equivalent Boron Content—The total equivalent boron
sufficient quantities of source or special nuclear material to be
content (EBC) shall not exceed 2.0 µg/gU.The list of elements
worthy of recovery.
to be considered in the EBC calculation shall be as recom-
mended in Practice C1233. The method of performing the
4. Isotopic Content
calculation shall be as indicated in Practice C1233.
4.1 For Commercial Grade Uranium Oxide with an isotopic
5.4 If the concentrations of any of the elements used in the
content of U between that of natural uranium and 5 %, the
calculations in 5.2 are reported as a less-than value, this
isotopic and radionuclide limits of Specification C996 shall
less-than value shall be used for any further calculations
apply. The specific isotopic and radionuclide measurements
involving the concentration of this element.
required by Specification C996 may be waived, provided that
5.5 Moisture Content—The moisture content of the uranium
the seller can demonstrate compliance through, for instance,
oxide shall not exceed 1 % by weight unless otherwise agreed
the seller’s quality assurance records.
upon by the buyer and seller.
4.2 For commercial uranium oxides not having an assay in
5.6 Ability to Flow—The Commercial Grade Uranium Ox-
the range set forth in 4.1, the isotopic requirements shall be as
ide shall be sufficiently free-flowing to permit sampling and
agreed upon between the buyer and seller.
powder handling.
5. Physical and Chemical Requirements
5.7 Particle Size—Particle size, size distribution and
method of determination shall be as agreed upon between the
5.1 Uranium Con
...

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