ASTM C1348-01(2008)
(Specification)Standard Specification for Blended Uranium Oxides with 235U Content of Less Than 5 % for Direct Hydrogen Reduction to Nuclear Grade Uranium Dioxide (Withdrawn 2013)
Standard Specification for Blended Uranium Oxides with <sup>235</sup>U Content of Less Than 5 % for Direct Hydrogen Reduction to Nuclear Grade Uranium Dioxide (Withdrawn 2013)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.
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Designation:C1348 −01(Reapproved 2008)
Standard Specification for
Blended Uranium Oxides with U Content of Less Than
5% for Direct Hydrogen Reduction to Nuclear Grade
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
of this standard to establish appropriate safety and health
by means of a direct reduction process. The UO powder
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
fabrication by pressing and sintering methods. This specifica-
2. Referenced Documents
tionappliestouraniumoxideswitha Uenrichmentlessthan
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
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
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
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. 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 service@astm.org. 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
C1348−01 (2008)
E11 Specification for Woven Wire Test Sieve Cloth and Test 5.3 Impurity Content—The impurity content of the
Sieves Commercial-Grade Uranium Oxide shall not exceed the indi-
E105 Practice for Probability Sampling of Materials vidual element limit specified in Table 1 on a uranium weight
basis. The summation of the contribution of each of the
2.2 ANSI Standard:
impurity elements listed in Table 1 shall not exceed 1000
NQA-1 Quality Assurance Program, Requirements for
µg/gU. The impurity content shall be determined using the
Nuclear Facilities
procedures described inTest Methods C696 or C1287, or both,
2.3 U.S. Government Document:
or as agreed upon between the buyer and the seller.
CFR Title 10 (Energy), Part 50, Domestic Licensing of
Production and Utilization Facilities 5.4 Equivalent Boron Content—The total equivalent boron
content (EBC) of the Commercial-Grade Uranium Oxide shall
3. Terminology not exceed 2.0 µg/gU. The list of elements to be considered in
the EBC calculation shall be as agreed upon between the buyer
3.1 Definitions—Terms shall be defined in accordance with
and the seller. The method of performing the calculation shall
Terminology C859, except the following.
be as indicated in Practice C1233.
3.2 Definitions of Terms Specific to This Standard:
5.5 If the concentrations of any of the elements used in the
3.2.1 Commercial-Grade Uranium Oxide—uranium triox-
calculations in 5.3 are reported as a less-than value, this
ide (UO ), U O , or a mixture of the two, made from
3 3 8
less-than value shall be used for any further calculations
unirradiated uranium. It is recognized that some contamination
involving the concentration of this element.
with reprocessed uranium may occur during routine process-
ing; this is acceptable, provided that the specification for
5.6 Bulk Density—Unless otherwise agreed upon between
Commercial-Grade Uranium Oxide, as set forth in 4.1, is met.
the buyer and the seller, the bulk density of the Commercial-
Grade Uranium Oxide shall be a minimum of 575 kg/m,as
4. Isotopic Content
determined by Test Method B329, or an alternative agreed
4.1 For Commercial-Grade Uranium Oxide with an isotopic upon between the buyer and the seller.
content of U between that of natural uranium and 5 %, the
5.7 Moisture Content—The moisture content of the
isotopic limits, including the requirements for reporting and
Commercial-Grade Uranium Oxide shall not exceed 1 % by
measurements of Specification C996 shall apply, unless other-
weight unless otherwise agreed upon by the buyer and the
wise agreed upon between the buyer and seller. The specific
seller.
isotopic measurements required by Specification C996 may be
5.8 Ability to Flow—The Commercial-Grade Uranium Ox-
waived, provided that the seller can demonstrate compliance
with Specification C996, for instance, through the seller’s ide shall be sufficiently free-flowing to permit sampling and
powder handling.
quality assurance records. U contents greater than that
specifiedinC996forEnrichedCommercialGradeUF6maybe
agreeduponbetweenthebuyerandsellersinceitisnotasafety
concern.
TABLE 1 Impurity Elements and Maximum Concentration Limits
4.2 For commercial uranium oxides not having an isotopic
Maximum Concentration Limit of Uranium,
concentration in the range set forth in 4.1, the isotopic
Element
µg/gU
requirements shall be as agreed upon between the buyer and
Aluminum 50
the seller.
Barium 5
Beryllium 100
Bismuth 3
5. Physical and Chemical Requirements
Calcium + magnesium 100
5.1 Uranium Content—The uranium content shall be deter- Carbon 100
Chlorine 100
mined using the procedures described inTest Methods C696 or
Chromium 100
C799, or as agreed upon between the buyer and the seller. The
Cobalt 80
Copper 100
minimum total uranium content shall also be agreed upon
Fluorine 100
between the buyer and the seller.
Iron 150
Lead 40
5.2 Oxygen-to-Uranium Ratio (O/U)—The O/U ratio of the
Manganese 50
Commercial-Grade Uranium Oxide shall be nominally be-
Molybdenum 200
tween 2.67 and 3.0. The O/U ratio shall be determined by Test
Nickel 80
Phosphorus 100
Methods C696 or by another method as agreed upon by the
Silicon 200
buyer and the seller.
Sodium 20
Tantalum 200
Thorium 10
Tin 50
Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
Titanium 50
4th Floor, New York, NY 10036, http://www.ansi.org.
Tungsten 100
Available from Standardization Documents Order Desk, DODSSP, Bldg. 4,
Vanadium 10
Section D, 700 Robbins Ave., Philadelphia, PA 19111-5098, http:// Zinc 20
www.dodssp.daps.mil.
C1348−01 (2008)
5.9 Particle Size—Based on visual observation, all of a contingent upon the material properties meeting the require-
representative sample of the Commercial-Grade Uranium Ox- ments of Sections 4-6.
ide shall pass through a 425-µm (No. 40) standard sieve
7.3 Referee Method—The buyer and seller shall agree to a
conforming to Specification E11, or as otherwise agreed upon
thirdpartyasarefereeintheeventofadisputeintheanalytical
between the buyer and the seller.Alternatively, as agreed upon
results.
between the buyer and the seller, the fraction not passing
through a 425-µm (No. 40) standard sieve shall be reported to 8. Certification
the buyer. Particle size, size distribution, and method of
8.1 The buyer shall be provided documents certifying that
determination shall be as agreed upon between the buyer and
the material meets all of the requirements of Sections 4-6.
the seller. Packing or agglomeration, or both, during shipping
8.2 Records of all data obtained from tests to certify that the
may be a concern.
mate
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