ASTM D7301 - 11

    Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose

    Active Standard ASTM D7301 | 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 properties of nuclear grade graphite billets with dimensions sufficient to meet the designers requirements for reflector blocks and core support structures, in a high temperature gas cooled reactor. The graphite classes specified here would be suitable for reactor core applications where neutron irradiation induced dimensional changes are not a significant design consideration.

    1.2 The purpose of this specification is to document the minimum acceptable properties and levels of quality assurance and traceability for nuclear grade graphite suitable for components subjected to low irradiation dose. Nuclear graphites meeting the requirements of Specification D7219 are also suitable for components subjected to low neutron irradiation dose.

    1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.


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

    ASME Standards

    NQA-1 Quality Assurance Program Requirements for Nuclear Facilities

    ASTM Standards

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

    C709 Terminology Relating to Manufactured Carbon and Graphite

    C781 Practice for Testing Graphite and Boronated Graphite Materials for High-Temperature 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

    D7219 Specification for Isotropic and Near-isotropic Nuclear Graphites


    ICS Code

    ICS Number Code 27.120.20 (Nuclear power plants. Safety)

    UNSPSC Code

    UNSPSC Code 11101507(Graphite)


    DOI: 10.1520/D7301-11

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