ASTM C996-04e1
(Specification)Standard Specification for Uranium Hexafluoride Enriched to Less Than 5 % 235U
Standard Specification for Uranium Hexafluoride Enriched to Less Than 5 % <sup> 235</sup>U
ABSTRACT
This specification covers nuclear grade uranium hexafluoride (UF6) that has been processed through an enrichment plant or produced by blending highly enriched uranium with other uranium to produce a concentration suitable for nuclear fuel fabrication. This specification defines the impurity and uranium isotope limits for the enriched commercial grade UF6 and for enriched reprocessed UF6. All materials should conform to the specified chemical, physical, and isotopic requirements.
SCOPE
1.1 This specification covers nuclear grade uranium hexafluoride (UF6) that either has been processed through an enrichment plant, or has been produced by the blending of Highly Enriched Uranium with other uranium to obtain uranium of any 235U concentration below 5 % and that is intended for fuel fabrication. The objectives of this specification are twofold: (1) To define the impurity and uranium isotope limits for Enriched Commercial Grade UF 6 so that, with respect to fuel design and manufacture, it is essentially equivalent to enriched uranium made from natural UF6; and (2) To define limits for Enriched Reprocessed UF6 to be expected if Reprocessed UF6 is to be enriched without dilution with Commercial Natural UF6. For such UF6, special provisions, not defined herein, may be needed to ensure fuel performance and to protect the work force, process equipment, and the environment.
1.2 This specification is intended to provide the nuclear industry with a standard for enriched UF6 that is to be used in the production of sinterable UO2 powder for fuel fabrication. In addition to this specification, the parties concerned may agree to other appropriate conditions.
1.3 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents or requirements for health and safety or for shipping. Observance of this specification does not relieve the user of the obligation to conform to all applicable international, federal, state, and local regulations for processing, shipping, or in any other way using UF6 (see, for example, TID-7016, DP-532, ORNL-NUREG-CSD-6, and DOE O474.1).
1.4 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
General Information
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Standards Content (Sample)
NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
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Designation: C996 – 04
Standard Specification for
235
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Uranium Hexafluoride Enriched to Less Than 5 % U
This standard is issued under the fixed designation C996; 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.
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´ NOTE—The table in Section 5.5 was corrected editorially in September 2004
1. Scope 2. Referenced Documents
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1.1 This specification covers nuclear grade uranium 2.1 ASTM Standards:
hexafluoride (UF ) that either has been processed through an C761 Test Methods for Chemical, Mass Spectrometric,
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enrichment plant, or has been produced by the blending of Spectrochemical, Nuclear, and Radiochemical Analysis of
Highly Enriched Uranium with other uranium to obtain ura- Uranium Hexafluoride
235
niumofany Uconcentrationbelow5 %andthatisintended C787 Specification for Uranium Hexafluoride for Enrich-
for fuel fabrication. The objectives of this specification are ment
twofold: (1) To define the impurity and uranium isotope limits C859 Terminology Relating to Nuclear Materials
for Enriched Commercial Grade UF so that, with respect to C1052 Practice for Bulk Sampling of Liquid Uranium
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fuel design and manufacture, it is essentially equivalent to Hexafluoride
enriched uranium made from natural UF ; and (2) To define C1295 Test Method for Gamma Energy Emission from
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limits for Enriched Reprocessed UF to be expected if Repro- Fission Products in Uranium Hexafluoride and Uranyl
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cessed UF is to be enriched without dilution with Commercial Nitrate Solution
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Natural UF . For such UF , special provisions, not defined C1561 Guide for Determination of Plutonium and Nep-
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herein, may be needed to ensure fuel performance and to tunium in Uranium Hexafluoride by Alpha Spectrometry
protect the work force, process equipment, and the environ- E29 Practice for Using Significant Digits in Test Data to
ment. Determine Conformance with Specifications
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1.2 This specification is intended to provide the nuclear 2.2 ANSI Standards:
industry with a standard for enriched UF that is to be used in ANSI/ASME NQA-1 Quality Assurance Requirements for
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the production of sinterable UO powder for fuel fabrication. Nuclear Facility Applications
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In addition to this specification, the parties concerned may ANSI N14.1 Nuclear Materials—Uranium Hexafluoride—
agree to other appropriate conditions. Packaging for Transport
1.3 The scope of this specification does not comprehen- 2.3 U.S. Government Documents:
sively cover all provisions for preventing criticality accidents Inspection, Weighing, and Sampling of Uranium Hexafluo-
or requirements for health and safety or for shipping. Obser- ride Cylinders, Procedure for Handling and Analysis of
vance of this specification does not relieve the user of the Uranium Hexafluoride, Vol. 1, DOE Report ORO-671-1,
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obligation to conform to all applicable international, federal, latest revision
state, and local regulations for processing, shipping, or in any Nuclear Safety Guide, U.S. NRC Report TID-7016, Rev. 2,
otherwayusingUF (see,forexample,TID-7016,DP-532,and 1978
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DOE O474.1). Clarke, H. K., Handbook of Nuclear Safety, DOE Report
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1.4 The values stated in SI units are to be regarded as the DP-532
standard. The values given in parentheses are for information
only.
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For referenced ASTM standards, visit the ASTM website, www.astm.org, or
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
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This specification is under the jurisdiction of ASTM Committee C26 on Standards volume information, refer to the standard’s Document Summary page on
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel the ASTM website.
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and Fertile Material Specifications. Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
CurrenteditionapprovedJune1,2004.PublishedJuly2004.Originallyapproved 4th Floor, New York, NY 10036.
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in 1983. Last previous edition approved in 1996 as C996 – 96. DOI: 10.1520/ AvailablefromU.S.GovernmentPrintingOfficeSuperintendentofDocuments,
732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401.
C0996-04E01.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
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C996 – 04
Code of Federal Regulations, Title 10, Part 50, (Appendix Additionally, if a measurement is taken over solid UF , the
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B) vapor pressure shall not exceed the values given below:
Control and Accountability of Nuclear Materials, DOE
50 kPa at 20°C (7 psia at 68°F), or
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69 kPa at 35°C (10 psia at 95°F)
Directive 5633.3B
2.4 Other Docume
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