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    Standards Related to E853 - E853

    E1006-13

    Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments

    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

    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

    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

    E2215-19

    Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels

    Also Available in these Collections:

    Developed By: Committee E10 on Nuclear Technology and Applications

    E482-16

    Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance

    Also Available in these Collections:

    Developed By: Committee E10 on Nuclear Technology and Applications

    E1214-11(2018)

    Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance

    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

    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