ASTM C967-20

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Designation: C967 − 13 C967 − 20
Standard Specification for
Uranium Ore Concentrate
This standard is issued under the fixed designation C967; 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
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 specification 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.after
SI units are provided for information only and are not considered standard.
1.4 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.
2. Referenced Documents
2.1 ASTM Standards:
C859 Terminology Relating to Nuclear Materials
C1022 Test Methods for Chemical and Atomic Absorption Analysis of Uranium-Ore Concentrate
C1075 Practices for Sampling Uranium-Ore Concentrate
C1380 Test Method for the Determination of Uranium Content and Isotopic Composition by Isotope Dilution Mass
Spectrometry (Withdrawn 2018)
C1843 Test Method for Determining Moisture Content in Uranium-Ore Concentrate
2.2 U.S. Government Documents:
Nuclear Materials Licensing Code of Federal Regulations, Energy Title 10, Chapter 1, Nuclear Regulatory Commission
Nuclear Materials Licensing Code of Federal Regulations, Title 49, Transportation Chapter 1, Materials Transportation Bureau
Nuclear Materials Licensing Code of Federal Regulations, Energy Part 50 (10CFR 50) Licensing of Domestic Production and
Utilization Facilities
2.3 ANSI Standard:
ANSI/ASME NQA-1 Quality Assurance Requirements for Nuclear Facility Applications
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.
Current edition approved Jan. 1, 2013Feb. 1, 2020. Published January 2013March 2020. Originally approved in 1981. Last previous edition approved in 20122013 as
C967 – 12.C967 – 13. DOI: 10.1520/C0967-13.10.1520/C0967-20.
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volume information, refer to the standard’s Document Summary page on the ASTM website.
The last approved version of this historical standard is referenced on www.astm.org.
Available from the Nuclear Regulatory Commission, Washington, DC, 20555-0001, www.nrc.gov.U. S. Nuclear Regulatory Commission (NRC), 11555 Rockville Pk.,
Rockville, MD 20852, http://www.nrc.gov.
Available from the Materials Transportation Bureau, 400 Seventh St., Washington, DC, 20590.
Available from American National Standards Institute (ANSI), 25 W. 43rd St., 4th Floor, New York, NY 10036, http://www.ansi.org.
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C967 − 20
3. Definitions
3.1 Except as otherwise defined herein, definitions of terms are as given in Terminology C859.
4. Chemical Composition
4.1 Uranium Content—The uranium content, as received, shall be a minimum of 65 mass %.
4.2 Isotopic Content—The isotopic content shall be that of naturally occurring uranium (0.711 6 0.001 g U per 100 g (see
Note 1). The U content shall not exceed the limits in Table 1.
NOTE 1—For ore concentrate from verifiable source (for example, through the seller’s quality assurance records), the U analysis is not normally
required unless otherwise agreed upon between the buyer and seller.
4.3 Insoluble Uranium—The uranium insoluble in nitric acid shall be a maximum of 0.10 mass % on a uranium basis.
4.4 Extractable Organic—Depending on the conversion process (dry route vs.versus wet route), the need for measurement of
extractable organic shall be agreed upon between buyer and seller (see Note 2).
NOTE 2—If a measurement is requested, a limit of 0.1 g per 100 g of ore concentrate shall be used.
4.5 Impurity Content—The impurity content shall be less
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