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About This Item

 

Full Description

Property data obtained with the recommended test methods identified herein may be used for research and development, design, manufacturing control, specifications, performance evaluation, and regulatory statutes pertaining to nuclear reactors that utilize graphite.
 

Document History

  1. ASTM C781-20


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

    • Most Recent
  2. ASTM C781-19


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

    • Historical Version
  3. ASTM C781-18

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    viewing


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

    • Historical Version
  4. ASTM C781-08(2014)


    Standard Practice for Testing Graphite and Boronated Graphite Materials for High-Temperature Gas-Cooled Nuclear Reactor Components

    • Historical Version
  5. ASTM C781-08


    Standard Practice for Testing Graphite and Boronated Graphite Materials for High-Temperature Gas-Cooled Nuclear Reactor Components

    • Historical Version
  6. ASTM C781-02


    Standard Practice for Testing Graphite and Boronated Graphite Components for High-Temperature Gas-Cooled Nuclear Reactors

    • Historical Version
  7. ASTM C781-96


    Standard Practice for Testing Graphite and Boronated Graphite Components for High-Temperature Gas-Cooled Nuclear Reactors

    • Historical Version