• ASTM D 7219 : 2008

    Superseded A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

    Standard Specification for Isotropic and Near-isotropic Nuclear Graphites

    Available format(s):  Hardcopy, PDF

    Superseded date:  11-11-2014

    Language(s):  English

    Published date:  01-05-2008

    Publisher:  American Society for Testing and Materials

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    Abstract - (Show below) - (Hide below)

    CONTAINED IN VOL. 05.04, 2017 Defines the classification, processing, and properties of nuclear grade graphite billets with dimensions sufficient to meet the designer's requirements for fuel elements, moderator or reflector blocks, in a high temperature gas cooled reactor.

    Scope - (Show below) - (Hide below)

    1.1 This specification covers the classification, processing, and properties of nuclear grade graphite billets with dimensions sufficient to meet the designers requirements for fuel elements, moderator or reflector blocks, 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 a significant design consideration.

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

    General Product Information - (Show below) - (Hide below)

    Committee D 02
    Document Type Standard
    Product Note Reconfirmed 2008
    Publisher American Society for Testing and Materials
    Status Superseded
    Superseded By
    Supersedes

    Standards Referenced By This Book - (Show below) - (Hide below)

    ASTM C 781 : 2018 Standard Practice for Testing Graphite Materials for Gas-Cooled Nuclear Reactor Components
    ASTM C 1793 : 2015 Standard Guide for Development of Specifications for Fiber Reinforced Silicon Carbide-Silicon Carbide Composite Structures for Nuclear Applications
    ASTM D 7301 : 2011 : R2015 Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose
    ASTM C 1783 : 2015 Standard Guide for Development of Specifications for Fiber Reinforced Carbon-Carbon Composite Structures for Nuclear Applications
    ASTM D 8093 : 2016 Standard Guide for Nondestructive Evaluation of Nuclear Grade Graphite
    ASTM D 8075 : 2016 Standard Guide for Categorization of Microstructural and Microtextural Features Observed in Optical Micrographs of Graphite

    Standards Referencing This Book - (Show below) - (Hide below)

    ASTM C 1233 : 2015 : REDLINE Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials
    IEEE/ASTM SI_10-2010 American National Standard for Metric Practice
    ASTM C 559 : 2016 : REDLINE Standard Test Method for Bulk Density by Physical Measurements of Manufactured Carbon and Graphite Articles
    ASME NQA 1 : 2015 Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015)
    ASTM C 838 : 2016 : REDLINE Standard Test Method for Bulk Density of As-Manufactured Carbon and Graphite Shapes
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