ASTM C1348-01(2008)

Standard Specification for Blended Uranium Oxides with ²³⁵U Content of Less Than 5 % for Direct Hydrogen Reduction to Nuclear Grade Uranium Dioxide (Withdrawn 2013)

ABSTRACT
This specification covers blended uranium oxides with a 235U content of less than 5% for direct hydrogen reduction to nuclear grade uranium dioxide. For commercial-grade uranium oxide with an isotopic content of 235U between that of natural uranium and 5%, the isotopic limits shall apply. Physical and chemical requirements include: uranium content, oxygen-to-uranium ratio, impurity content, equivalent boron content, bulk density, moisture content, ability to flow, particle size, and reduction and sinterability. Maximum concentration limit is specified for impurity elements such as: aluminum, barium, beryllium, bismuth, calcium+magnesium, carbon, chlorine, chromium, cobalt, copper, fluorine, iron, lead, manganese, molybdenum, nickel, phosphorus, silicon, sodium, tantalum, thorium, tin, titanium, tungsten, vanadium, and zinc. The identity of a lot shall be retained throughout.
SCOPE
1.1 This specification covers blended uranium trioxide (UO3), U3O8, or mixtures of the two, powders that are intended for conversion into a sinterable uranium dioxide (UO2) powder by means of a direct reduction process. The UO2 powder product of the reduction process must meet the requirements of Specification C 753 and be suitable for subsequent UO2 pellet fabrication by pressing and sintering methods. This specification applies to uranium oxides with a 235U enrichment less than 5 %.
1.2 This specification includes chemical, physical, and test method requirements for uranium oxide powders as they relate to the suitability of the powder for storage, transportation, and direct reduction to UO2 powder. This specification is applicable to uranium oxide powders for such use from any source.
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 uranium oxide powders (see 2.2 and 2.3).
1.4 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
1.5 The following safety hazards caveat pertains only to the test methods portion of the annexes in this specification: This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.
WITHDRAWN RATIONALE
This specification covers blended uranium trioxide (UO3), U3O8, or mixtures of the two, powders that are intended for conversion into a sinterable uranium dioxide (UO2) powder by means of a direct reduction process. The UO2 powder product of the reduction process must meet the requirements of Specification  and be suitable for subsequent UO2 pellet fabrication by pressing and sintering methods. This specification applies to uranium oxides with a 235U enrichment less than 5���%.
Formerly under the jurisdiction of Committee C26 on Nuclear Fuel Cycle, this test method was withdrawn in January 2013. This standard is being withdrawn without replacement due to its limited use by industry.

General Information

• Status: Withdrawn
• Publication Date: 31-May-2008
• Withdrawal Date: 31-Dec-2012
• 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 C1348-01 - Standard Specification for Blended Uranium Oxides with a ²³⁵U Content of Less Than 5 % for Direct Hydrogen Reduction to Nuclear Grade Uranium Dioxide
• Effective Date: 01-Jun-2008
• 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-Jun-2008

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:C1348 −01(Reapproved 2008)
Standard Specification for
235
Blended Uranium Oxides with U Content of Less Than
5% for Direct Hydrogen Reduction to Nuclear Grade
1
Uranium Dioxide
This standard is issued under the fixed designation C1348; 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.
INTRODUCTION
This specification is intended to provide the nuclear industry with a general standard for such
uranium oxide powders. It recognizes the diversity of conversion processes and the many special
requirements for chemical and physical characterization that may be imposed by the end use of the
powder. It is anticipated, therefore, that this specification may be supplemented with additional
requirements by agreement between the buyer and the seller.
1. Scope 1.5 The following safety hazards caveat pertains only to the
test methods portion of the annexes in this specification: This
1.1 This specification covers blended uranium trioxide
standard does not purport to address all of the safety concerns,
(UO ),U O ,ormixturesofthetwo,powdersthatareintended
3 3 8
if any, associated with its use. It is the responsibility of the user
for conversion into a sinterable uranium dioxide (UO ) powder
2
of this standard to establish appropriate safety and health
by means of a direct reduction process. The UO powder
2
practices and determine the applicability of regulatory limita-
product of the reduction process must meet the requirements of
tions prior to use.
Specification C753 and be suitable for subsequent UO pellet
2
fabrication by pressing and sintering methods. This specifica-
2. Referenced Documents
235
tionappliestouraniumoxideswitha Uenrichmentlessthan
2
2.1 ASTM Standards:
5%.
B329 Test Method for Apparent Density of Metal Powders
1.2 This specification includes chemical, physical, and test
and Compounds Using the Scott Volumeter
method requirements for uranium oxide powders as they relate
C696 Test Methods for Chemical, Mass Spectrometric, and
to the suitability of the powder for storage, transportation, and
Spectrochemical Analysis of Nuclear-Grade Uranium Di-
directreductiontoUO powder.Thisspecificationisapplicable
2
oxide Powders and Pellets
to uranium oxide powders for such use from any source.
C753 Specification for Nuclear-Grade, Sinterable Uranium
1.3 The scope of this specification does not comprehen-
Dioxide Powder
sively cover all provisions for preventing criticality accidents,
C799 Test Methods for Chemical, Mass Spectrometric,
for health and safety, or for shipping. Observance of this
Spectrochemical, Nuclear, and RadiochemicalAnalysis of
specification does not relieve the user of the obligation to
Nuclear-Grade Uranyl Nitrate Solutions
conform to all international, national, state, and local regula-
C859 Terminology Relating to Nuclear Materials
tions for processing, shipping, or any other way of using
C996 Specification for Uranium Hexafluoride Enriched to
235
uranium oxide powders (see 2.2 and 2.3).
Less Than 5 % U
C1233 Practice for Determining Equivalent Boron Contents
1.4 The values stated in SI units are to be regarded as the
of Nuclear Materials
standard. The values given in parentheses are for information
C1287 Test Method for Determination of Impurities in
only.
Nuclear Grade Uranium Compounds by Inductively
Coupled Plasma Mass Spectrometry
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
2
and Fertile Material Specifications. For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Current edition approved June 1, 2008. Published August 2008. Originally contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
approved in 1996. Last previous edition approved in 2001 as C1348 – 01. DOI: Standards volume information, refer to the standard’s Document Summary page on
10.1520/C1348-01R08. 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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C1348−01 (2008)
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3
basis. The summation of the contribution of each of the
2.2 ANSI Standard:
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NQA-1 Quality Assurance Program, Requirements for
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...