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  • ASTM C 1233 : 2015 : REDLINE

    Current The latest, up-to-date edition.

    Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials

    Available format(s):  PDF

    Language(s):  English

    Published date:  01-06-2015

    Publisher:  American Society for Testing and Materials

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    Abstract - (Show below) - (Hide below)

    CONTAINED IN VOL. 12.01, 2015 Defines a recommended practice for the calculation of the Equivalent Boron Content (EBC) for nuclear materials.

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    1.1This standard details a recommended practice for the calculation of the Equivalent Boron Content (EBC) for nuclear materials. The EBC is used to provide a measure of the macroscopic neutron absorption cross section of a nuclear material. EBC factors for the natural elements are determined from their atomic masses and thermal neutron absorption cross sections. This practice is illustrated by using EBC factors that are based on thermal neutron (2200 m/s) absorption cross sections. Other EBC factors may be used depending upon the actual neutron energy spectrum.

    1.2The EBC is a characteristic of a homogeneous material. Characterization of inhomogeneous materials and calculation of neutron multiplication factors require techniques that are beyond the scope of this practice.

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

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

    Committee C 26
    Document Type Redline
    Publisher American Society for Testing and Materials
    Status Current

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

    ASTM C 1462 : 2000 : R2005 Standard Specification for Uranium Metal Enriched to More than 15% and Less Than 20%235 U
    ASTM C 1065 : 2008 : R2015 Standard Specification for Nuclear-Grade Zirconium Oxide Powder
    ASTM C 785 : 2008 : R2015 Standard Specification for Nuclear-Grade Aluminum Oxide Pellets
    ASTM D 7301 : 2011 : R2015 Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose
    ASTM C 1462 : 2000 Standard Specification for Uranium Metal Enriched to More than 15% and Less Than 20%235 U
    ASTM C 1334 : 2005 : R2010 Standard Specification for Uranium Oxides with a 235U Content of Less Than 5 % for Dissolution Prior to Conversion to Nuclear-Grade Uranium Dioxide
    ASTM C 1334 : 2005 Standard Specification for Uranium Oxides with a 235U Content of Less Than 5 % for Dissolution Prior to Conversion to Nuclear-Grade Uranium Dioxide
    ISO 13463:1999 Nuclear-grade plutonium dioxide powder for fabrication of light water reactor MOX fuel — Guidelines to help in the definition of a product specification
    ASTM C 785 : 2008 Standard Specification for Nuclear-Grade Aluminum Oxide Pellets
    ASTM C 799 : 2012 Standard Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-Grade Uranyl Nitrate Solutions
    ASTM C 781 : 2008 : R2014 Standard Practice for Testing Graphite and Boronated Graphite Materials for High-Temperature Gas-Cooled Nuclear Reactor Components
    ASTM C 776 : 2017 : REDLINE Standard Specification for Sintered Uranium Dioxide Pellets for Light Water Reactors
    ASTM C 1065 : 2008 Standard Specification for Nuclear-Grade Zirconium Oxide Powder
    ASTM C 1462 : 2000 : R2013 Standard Specification for Uranium Metal Enriched to More than 15 % and Less Than 20 % 235U
    ASTM D 7219 : 2008 : R2014 Standard Specification for Isotropic and Near-isotropic Nuclear Graphites
    ASTM C 781 : 2008 Standard Practice for Testing Graphite and Boronated Graphite Materials for High-Temperature Gas-Cooled Nuclear Reactor Components
    ASTM C 788 : 2003 : R2015 Standard Specification for Nuclear-Grade Uranyl Nitrate Solution or Crystals
    BS ISO 13463:1999 Nuclear-grade plutonium dioxide powder for fabrication of light water reactor MOX fuel. Guidelines to help in the definition of a product specification
    ASTM C 1462 : 2000 : R2008 Standard Specification for Uranium Metal Enriched to More than 15 % and Less Than 20 % 235U
    ASTM C 788 : 2003 : R2009 Standard Specification for Nuclear-Grade Uranyl Nitrate Solution or Crystals
    ASTM C 1783 : 2015 Standard Guide for Development of Specifications for Fiber Reinforced Carbon-Carbon Composite Structures for Nuclear Applications
    ASTM C 1793 : 2015 Standard Guide for Development of Specifications for Fiber Reinforced Silicon Carbide-Silicon Carbide Composite Structures for Nuclear Applications
    ASTM C 1334 : 2005 : EDT 1 Standard Specification for Uranium Oxides with a 235U Content of Less Than 5 % for Dissolution Prior to Conversion to Nuclear-Grade Uranium Dioxide
    ASTM C 833 : 2017 : REDLINE Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets for Light Water Reactors
    ASTM C 708 : 2016 : REDLINE Standard Specification for Nuclear-Grade Beryllium Oxide Powder
    ASTM C 697 : 2016 : REDLINE Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Plutonium Dioxide Powders and Pellets
    ASTM C 788 : 2003 Standard Specification for Nuclear-Grade Uranyl Nitrate Solution or Crystals
    ASTM C 698 : 2016 : REDLINE Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Mixed Oxides ((U, Pu)O2)
    ASTM D 7301 : 2011 Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose
    ASTM D 7219 : 2008 Standard Specification for Isotropic and Near-isotropic Nuclear Graphites
    ASTM C 1334 : 2005 : R2016 : EDT 1 Standard Specification for Uranium Oxides with a 235U Content of Less Than 5 % for Dissolution Prior to Conversion to Nuclear-Grade Uranium Dioxide
    ASTM C 761 : 2018 : REDLINE Standard Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Uranium Hexafluoride

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

    ASTM C 799 : 2012 Standard Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-Grade Uranyl Nitrate Solutions
    ASTM C 698 : 2016 : REDLINE Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Mixed Oxides ((U, Pu)O2)
    ASTM C 696 : 2011 : REDLINE Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets
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