• ASTM C 1868 : 2018

    Current The latest, up-to-date edition.

    Standard Practice for Ceramographic Preparation of UO2 and Mixed Oxide (U,Pu)O2 Pellets for Microstructural Analysis

    Available format(s):  Hardcopy, PDF

    Language(s):  English

    Published date:  01-01-2018

    Publisher:  American Society for Testing and Materials

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    Abstract - (Show below) - (Hide below)

    CONTAINED IN VOL. 12.01, 2018 Specifies the procedure for preparing nuclear-grade uranium dioxide (UO2) or mixed uraniumplutonium dioxide (MOX or (U,Pu)O[2])), sintered and nonirradiated pellets for subsequent microstructural analysis (hereafter referred to as ceramographic examination).

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    1.1This practice describes the procedure for preparing nuclear-grade uranium dioxide (UO2) or mixed uranium-plutonium dioxide (MOX or (U,Pu)O2)), sintered and non-irradiated pellets for subsequent microstructural analysis (hereafter referred to as ceramographic examination).

    1.2The ceramographic examination is performed to confirm that the microstructure of the sintered pellet is in compliance with the fuel specification, for example as defined in Specifications C776 and C833, as a function of the initial raw material properties and manufacturing process parameters.

    1.3The microstructure of a ceramic pellet includes: grain size, porosity size and distribution, and phase distribution for (U,Pu)O2 pellets, that is, Pu-rich cluster size and distribution.2

    1.4The microstructural characteristics of the pellet are accessible after preparation which involves: sawing, mounting in a resin, surface polishing, and chemical etching, thermal etching, or both.

    1.5This practice describes the preparation processes mentioned in 1.4; it does not discuss the associated sampling practices (for example, Practice E105) or ceramographic examination methods (for example, the methods for determining average grain size are covered in Test Method E112).

    1.6Due to the radiotoxicity associated with these nuclear materials, all operations described in this practice should be performed in glovebox for (U,Pu)O2 pellets and in a hood for UO2 pellets.

    1.7The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

    1.8This 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.

    1.9This 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.

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

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

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

    ASTM C 833 : 2017 Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets for Light Water Reactors
    ASTM C 859 : 2023 Standard Terminology Relating to Nuclear Materials
    ASTM C 859 : 2014 : REV B Standard Terminology Relating to Nuclear Materials
    ASTM C 776 : 2017 : R2022 Standard Specification for Sintered Uranium Dioxide Pellets for Light Water Reactors
    ASTM C 859 : 2024 Standard Terminology Relating to Nuclear Materials
    ASTM C 833 : 2023 Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets for Light Water Reactors
    ASTM D 1193 : 1977 : R1983 : EDT 1 Standard Specification for Reagent Water
    ASTM E 105 : 2016 : REDLINE Standard Practice for Probability Sampling of Materials
    ASTM E 105 : 2021 Standard Guide for Probability Sampling of Materials
    ASTM D 1193 : 2006 : R2011 Standard Specification for Reagent Water
    ASTM C 859 : 2022 Standard Terminology Relating to Nuclear Materials
    ASTM C 859 : 2022 : REV A Standard Terminology Relating to Nuclear Materials
    ASTM D 1193 : 1991 Standard Specification for Reagent Water
    ASTM C 833 : 2017 : REDLINE Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets for Light Water Reactors
    ASTM C 776 : 2017 Standard Specification for Sintered Uranium Dioxide Pellets for Light Water Reactors
    ASTM E 105 : 2016 Standard Practice for Probability Sampling of Materials
    ASTM D 1193 : 1970 Standard Specification For Reagent Water
    ASTM D 1193 : 2006 Standard Specification for Reagent Water
    ASTM E 112 : 2013 : R2021 Standard Test Methods for Determining Average Grain Size
    ASTM E 112 : 2013 Standard Test Methods for Determining Average Grain Size
    ASTM D 1193 : 1999 Standard Specification for Reagent Water
    ASTM D 1193 : 2006 : R2018 Standard Specification for Reagent Water
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