ASTM WK71932

    New Practice for Sampling Gaseous Uranium Hexafluoride Using Zeolite in a Single-Use Destructive Assay Sampler

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    Developed by Subcommittee: C26.02 | Committee C26 | Contact Staff Manager


    1. Scope

    1.1 This practice is applicable to sampling gaseous uranium hexafluoride (UF6) from processing facilities, isotope enrichment cascades or storage cylinders, using the sorbent properties of zeolite in a single-use destructive assay (SUDA) sampler. 1.2 This practice is based on the SUDA method developed at Pacific Northwest National Laboratory (1) for collection of samples of UF6 for determination of uranium isotopic content for nuclear material safeguards and other applications. 1.3 UF6 collected is converted to uranyl fluoride (UO2F2), allowing samples to be handled and categorized for transport under less stringent conditions than are required for UF6. 1.4 The scope of this practice does not include provisions for preventing criticality. 1.5 UnitsThe values stated in SI units are to be regarded as standard. When non-SI units are provided, they are for information only. 1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. 1.7 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 Recommendation issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.


    Nuclear material safeguards; uranium hexafluoride sampling; enrichment; uranium isotopic composition; uranium isotope ratios


    This practice will provide a standard procedure for utilization of a single-use destructive assay sampler for collection of gaseous uranium hexafluoride for subsequent measurement of isotopic content. It will be used for processing facilities, isotope enrichment cascades or UF6 storage cylinders in the nuclear industry.

    The title and scope are in draft form and are under development within this ASTM Committee.

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    Work Item Status

    Date Initiated:

    Technical Contact:
    Michael Brisson


    C26.02 (20-02)

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