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    Standards Related to E482 - E482

    E944-19

    Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance

    Also Available in these Collections:

    Developed By: Committee E10 on Nuclear Technology and Applications

    E1035-18

    Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures

    Also Available in these Collections:

    Developed By: Committee E10 on Nuclear Technology and Applications

    E1005-16

    Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance

    Also Available in these Collections:

    Developed By: Committee E10 on Nuclear Technology and Applications

    E910-18

    Standard Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance

    Also Available in these Collections:

    Developed By: Committee E10 on Nuclear Technology and Applications

    E853-18

    Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results

    Also Available in these Collections:

    Developed By: Committee E10 on Nuclear Technology and Applications

    E900-15e2

    Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials

    Also Available in these Collections:

    Developed By: Committee E10 on Nuclear Technology and Applications

    E854-19

    Standard Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance

    Also Available in these Collections:

    Developed By: Committee E10 on Nuclear Technology and Applications

    E2005-10(2015)

    Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields

    Also Available in these Collections:

    Developed By: Committee E10 on Nuclear Technology and Applications

    E844-18

    Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance

    Also Available in these Collections:

    Developed By: Committee E10 on Nuclear Technology and Applications