ASTM D7219 - 19

    Standard Specification for Isotropic and Near-isotropic Nuclear Graphites

    Active Standard ASTM D7219 | Developed by Subcommittee: D02.F0

    Book of Standards Volume: 05.05


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    1. Scope

    1.1 This specification covers the classification, processing, and typical properties of as-manufactured nuclear grade graphite billets with dimensions sufficient to meet the designer’s requirements for fuel elements, moderator or reflector blocks, in a high temperature reactor. The graphite classes specified here may be suitable for reactor core applications where dimensional change due to fast neutron irradiation has a significant impact on design, provided they meet the requirements of the ASME code.

    1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. (See IEEE/ASTM SI 10.)

    1.3 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.

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

    ASTM Standards

    C559 Test Method for Bulk Density by Physical Measurements of Manufactured Carbon and Graphite Articles

    C781 Practice for Testing Graphite Materials for Gas-Cooled Nuclear Reactor Components

    C838 Test Method for Bulk Density of As-Manufactured Carbon and Graphite Shapes

    C1233 Practice for Determining Equivalent Boron Contents of Nuclear Materials

    D346 Practice for Collection and Preparation of Coke Samples for Laboratory Analysis

    D2638 Test Method for Real Density of Calcined Petroleum Coke by Helium Pycnometer

    D4175 Terminology Relating to Petroleum Products, Liquid Fuels, and Lubricants


    ICS Code

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

    UNSPSC Code

    UNSPSC Code 11101507(Graphite)


    Referencing This Standard
    Link Here
    Link to Active (This link will always route to the current Active version of the standard.)

    DOI: 10.1520/D7219-19

    Citation Format

    ASTM D7219-19, Standard Specification for Isotropic and Near-isotropic Nuclear Graphites, ASTM International, West Conshohocken, PA, 2019, www.astm.org

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