ASTM C967-02
(Specification)Standard Specification for Uranium Ore Concentrate
Standard Specification for Uranium Ore Concentrate
SCOPE
1.1 This specification covers uranium ore concentrate containing a minimum of 65 mass % uranium.
1.2 This specification does not include requirements for health and safety. Observance of this standard does not relieve the user of the obligation to be aware of and conform to all applicable international, national, state, and local regulations pertaining to possessing, shipping, or using source nuclear material (see 2.2).
1.3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
General Information
Relations
Standards Content (Sample)
NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Please contact ASTM International (www.astm.org) for the latest information.
Designation: C 967 – 02
Standard Specification for
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Uranium Ore Concentrate
This standard is issued under the fixed designation C 967; 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 uranium
ore concentrate. Material conforming to this specification will generally meet the requirements for
conversion to uranium hexafluoride. However, the converter may relax or supplement this specifica-
tion upon mutual agreement with the customer.
1. Scope Nuclear Materials Licensing Code of Federal Regulations,
Energy Part 50 (10CFR 50) Licensing of Domestic Pro-
1.1 This specification covers uranium ore concentrate con-
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duction and Utilization Facilities
taining a minimum of 65 mass % uranium.
2.3 ANSI Standard:
1.2 This specification does not include requirements for
ANSI/ASME NQA-1 Quality Assurance Requirements for
health and safety. Observance of this specification does not
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Nuclear Facility Applications
relieve the user of the obligation to be aware of and conform to
all applicable international, national, state, and local regula-
3. Terminology Definitions
tions pertaining to possessing, shipping, or using source
3.1 Except as otherwise defined herein, definitions of terms
nuclear material (see 2.2).
are as given in Terminology C 859C 859.
1.3 The values stated in SI units are to be regarded as the
standard. The values given in parentheses are for information
4. Chemical Composition
only.
4.1 Uranium Content—The uranium content, as received,
2. Referenced Documents shall be a minimum of 65 mass %.
4.2 Isotopic Content—The isotopic content shall be that of
2.1 ASTM Standards:
235
2 naturally occurring uranium (0.7105 6 0.0005 g U per 100
C 859 Terminology Relating to Nuclear Materials
234
g. The U content shall not exceed the limits in Table 1.
C 1022 Test Methods for Chemical and Atomic Absorption
2
4.3 Insoluble Uranium—The uranium insoluble in nitric
Analysis of Uranium-Ore Concentrate
2 acid shall be a maximum of 0.10 mass % on a uranium basis.
C 1075 Practices for Sampling Uranium-Ore Concentrate
4.4 ExtractableOrganic—Theextractableorganicshallbea
C 1380 Test Method for the Determination of Uranium
maximum of 0.10 weight % on an as-received basis of an
Content and Isotopic Composition by Isotope Dilution
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undried sample.
Mass Spectrometry
4.5 Impurity Content—The impurity content shall be less
2.2 U.S. Government Documents:
thanthemaximumlimitsspecifiedinTable1.Thesellershould
Nuclear Materials Licensing Code of Federal Regulations
3 advise all parties of the presence of toxic elements such asAg,
Title 10, Chapter 1, Nuclear Regulatory Commission
As, Ba, Cd, Cr(VI), Hg, Pb, and Se in the uranium ore
Nuclear Materials Licensing Code of Federal Regulations,
concentrate.
Title 49, Transportation Chapter 1, Materials Transporta-
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tion Bureau
5. Physical Properties
5.1 Particle Size—All of a representative sample (Section
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6) shall pass through a sieve with an aperature of ⁄4 in.
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
5.2 Ability to Flow—Concentrate shall be sufficiently free-
and Fertile Material Specifications.
flowing to permit sampling.
Current edition approved Feb. 10, 2002. Published June 2002. Originally
5.3 Foreign Matter—Concentrate shall be free of all mate-
published as C 967 – 81. Last previous edition C 967 – 87(1996).
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Annual Book of ASTM Standards, Vol 12.01. rials and objects that: (a) are not produced as a constituent of
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Available from the Nuclear Regulatory Commission, 1717 H Street, N. W.,
Washington, DC 20555.
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Available from the Materials Transportation Bureau, 400 Seventh St., Wash- Available from American National Standards Institute, 11 W. 42nd St., 13th
ington, DC, 20590. Floor, New York, NY 10036.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
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NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Please contact ASTM International (www.astm.org) for the latest information.
C967–02
TABLE 1 Impurities and Maximum Concentration Limits
A
Maximum Concentration Limit (Mass %, Uranium Basis)
Impurity
Limit Without
C
Limit Without Rejection
B
Penalty
As 0.05 0.10
B 0.005 0.10
Ca 0.05 1.00
Carbonate 0.20 0.50
F 0.01 0.10
D
Halogens 0.05 0.10
Fe 0.15 1.00
Mg 0.02 0.50
E
Moisture 2.0 5.0
Mo 0.10 0.30
P 0
...
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