ASTM C996 - 10

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

    Active Standard ASTM C996 | Developed by Subcommittee: C26.02

    Book of Standards Volume: 12.01


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    ASTM C996

    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.

    This abstract is a brief summary of the referenced standard. It is informational only and not an official part of the standard; the full text of the standard itself must be referred to for its use and application. ASTM does not give any warranty express or implied or make any representation that the contents of this abstract are accurate, complete or up to date.

    1. 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 UF6 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, 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.


    2. Referenced Documents (purchase separately) The documents listed below are referenced within the subject standard but are not provided as part of the standard.

    ASTM Standards

    C761 Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Uranium Hexafluoride

    C787 Specification for Uranium Hexafluoride for Enrichment

    C859 Terminology Relating to Nuclear Materials

    C1052 Practice for Bulk Sampling of Liquid Uranium Hexafluoride

    C1703 Practice for Sampling of Gaseous Uranium Hexafluoride

    E29 Practice for Using Significant Digits in Test Data to Determine Conformance with Specifications

    ANSI Standards

    ANSIN14.1 Nuclear Materials--Uranium Hexafluoride--Packaging for Transport

    U.S. Government Documents

    CodeofFederalRegulat Part 50, (Appendix B)

    Other Document

    TheUF6Manual:GoodHan United States Enrichment Corporation Report USEC-651, latest revision Available from United States Enrichment Corporation, 6903 Rockledge Drive, Bethesda, MD 20817.


    ICS Code

    ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)

    UNSPSC Code

    UNSPSC Code 15131503(Enriched uranium)


    DOI: 10.1520/C0996-10

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