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  • ASTM E 185 : 1998

    Superseded A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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    Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E706 (IF)

    Available format(s): 

    Superseded date:  11-11-2014


    Published date:  31-12-2010

    Publisher:  American Society for Testing and Materials

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    1.1 This practice covers procedures for monitoring the radiation-induced changes in the mechanical properties of ferritic materials in the beltline of light-water cooled nuclear power reactor vessels. This practice includes guidelines for designing a minimum surveillance program, selecting materials, and evaluating test results.

    1.2 This practice was developed for all light-water cooled nuclear power reactor vessels for which the predicted maximum neutron fluence ( > 1 MeV) at the end of the design lifetime exceeds 1 X 10 17 n/cm (1 X 10 21 n/m ) at the inside surface of the reactor vessel.

    1.3 This practice does not provide procedures for monitoring the radiation induced changes in properties beyond the design life, but the procedure described may provide guidance for developing such a surveillance program.

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    Committee E 10
    Document Type Standard Practice
    Publisher American Society for Testing and Materials
    Status Superseded
    Superseded By

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

    ASTM E 706 : 2016 Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards
    ASTM E 531 : 2013 Standard Practice for Surveillance Testing of High-Temperature Nuclear Component Materials (Withdrawn 2022)
    ASTM E 636 : 2020 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels
    ASTM E 509/E509M : 2014 Standard Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels
    ASTM E 900 : 2015 : EDT 2 Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
    ASTM E 1005 : 2016 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
    ASTM E 1006 : 2013 Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
    ASTM E 1253 : 2013 Standard Guide for Reconstitution of Irradiated Charpy-Sized Specimens
    ASTM E 2956 : 2014 Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
    ASTM E 853 : 2018 Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results
    ASTM E 1214 : 2011 : R2018 Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance
    ASTM E 2215 : 2019 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
    ASTM E 1018 : 2020 : EDT 1 Standard Guide for Application of ASTM Evaluated Cross Section Data File
    ASTM E 1297 : 2018 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium
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