ASTM C996-04

Standard Specification for Uranium Hexafluoride Enriched to Less Than 5 % ²³⁵U

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

• Status: Historical
• Publication Date: 31-May-2004
• 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 C996-96 - Standard Specification for Uranium Hexafluoride Enriched to Less Than 5% 235U1
• Effective Date: 01-Jun-2004
• Replaced By: ASTM C996-04e1 - Standard Specification for Uranium Hexafluoride Enriched to Less Than 5 % ²³⁵U
• Effective Date: 01-Jun-2004
• Referred By: ASTM C788-03(2021) - Standard Specification for Nuclear-Grade Uranyl Nitrate Solution or Crystals
• Effective Date: 01-Jun-2004
• Referred By: ASTM C1913-21 - Standard Practice for Sampling Gaseous Uranium Hexafluoride Using Zeolite in Single-Use Destructive Assay Sampler
• Effective Date: 01-Jun-2004
• 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-2004
• Referred By: ASTM C1462-21 - Standard Specification for Uranium Metal Enriched to Less Than 20 % <sup> 235</sup >U
• Effective Date: 01-Jun-2004
• Referred By: ASTM C1287-18 - Standard Test Method for Determination of Impurities in Nuclear Grade Uranium Compounds by Inductively Coupled Plasma Mass Spectrometry
• Effective Date: 01-Jun-2004
• Referred By: ASTM C1883-19 - Standard Practice for Sampling of Gaseous Enriched Uranium Hexafluoride
• Effective Date: 01-Jun-2004
• Referred By: ASTM C1295-15 - Standard Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium Hexafluoride and Uranyl Nitrate Solution
• Effective Date: 01-Jun-2004
• Referred By: ASTM C1689-21 - Standard Practice for Subsampling of Uranium Hexafluoride
• Effective Date: 01-Jun-2004
• Referred By: ASTM C776-17(2022) - Standard Specification for Sintered Uranium Dioxide Pellets for Light Water Reactors
• Effective Date: 01-Jun-2004
• Referred By: ASTM C1647-20 - Standard Practice for Removal of Uranium or Plutonium, or both, for Impurity Assay in Uranium or Plutonium Materials
• Effective Date: 01-Jun-2004
• Referred By: ASTM C1871-22 - Standard Test Method for Determination of Uranium Isotopic Composition by the Double Spike Method Using a Thermal Ionization Mass Spectrometer
• Effective Date: 01-Jun-2004
• Referred By: ASTM C1672-17 - Standard Test Method for Determination of Uranium or Plutonium Isotopic Composition or Concentration by the Total Evaporation Method Using a Thermal Ionization Mass Spectrometer
• Effective Date: 01-Jun-2004
• Referred By: ASTM C1477-19 - Standard Test Method for Isotopic Abundance Analysis of Uranium Hexafluoride and Uranyl Nitrate Solutions by Multi-Collector, Inductively Coupled Plasma-Mass Spectrometry
• Effective Date: 01-Jun-2004

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 996 – 04
Standard Specification for
235
1
Uranium Hexafluoride Enriched to Less Than 5 % U
This standard is issued under the fixed designation C 996; 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.
1 e1
´ NOTE—DO NOT USE THIS VERSION!!!! C996–04 was replaced with C996–04 .
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 C 761 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 C 787 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 C 859 Terminology Relating to Nuclear Materials
for Enriched Commercial Grade UF so that, with respect to C 1052 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 C 1295 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
6
cessed UF is to be enriched without dilution with Commercial C 1561 Guide for the Measurement of Plutonium and Nep-
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Natural UF . For such UF , special provisions, not defined tunium in UF
6 6 6
herein, may be needed to ensure fuel performance and to E29 Practice for Using Significant Digits in Test Data to
protect the work force, process equipment, and the environ- Determine Conformance with Specifications
3
ment. 2.2 ANSI Standards:
1.2 This specification is intended to provide the nuclear ANSI/ASME NQA-1 Quality Assurance Requirements for
industry with a standard for enriched UF that is to be used in Nuclear Facility Applications
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the production of sinterable UO powder for fuel fabrication. ANSI N14.1 Nuclear Materials—Uranium Hexafluoride—
2
In addition to this specification, the parties concerned may Packaging for Transport
agree to other appropriate conditions. 2.3 U.S. Government Documents:
1.3 The scope of this specification does not comprehen- Inspection, Weighing, and Sampling of Uranium Hexafluo-
sively cover all provisions for preventing criticality accidents ride Cylinders, Procedure for Handling and Analysis of
or requirements for health and safety or for shipping. Obser- Uranium Hexafluoride, Vol. 1, DOE Report ORO-671-1,
4
vance of this specification does not relieve the user of the latest revision
obligation to conform to all applicable international, federal, Nuclear Safety Guide, U.S. NRC Report TID-7016, Rev. 2,
state, and local regulations for processing, shipping, or in any 1978
otherwayusingUF (see,forexample,TID-7016,DP-532,and Clarke, H. K., Handbook of Nuclear Safety, DOE Report
6
4
DOE O474.1). DP-532
1.4 The values stated in SI units are to be regarded as the Code of Federal Regulations, Title 10, Part 50, (Appendix
4
standard. The values given in parentheses are for information B)
only.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
1
Invalid Version: See edit note above. This specification is under the Standards volume information, refer to the standard’s Document Summary page on
jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct the ASTM website.
3
responsibility of Subcommittee C26.02 on Fuel and Fertile Material Specifications. Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
Invalid Version: See edit note above.Current edition approved June 1, 2004. 4th Floor, New York, NY 10036.
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Published July 2004. Originally approved in 1983. Last previous edition approved AvailablefromU.S.GovernmentPrintingOfficeSuperintendentofDocuments,
in 1996 as C 996 – 96. 732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401.
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.
C996–04
Control and Accountability of Nuclear Materials, DOE
862 kPa at 112°C (125 psia at 235°F)
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Directive 56
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