ASTM WK40958

    Revision of E636 - 10 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E 706 (IH)

    (What is a Work Item?)

    Active Standard: E636 - 14

    Developed by Subcommittee: E10.02 | Committee E10 | Contact Staff Manager


    1. Rationale

    ASTM E636 is being revised, with the main purpose of acknowledging the standardization of fracture toughness tests at impact loading rates on precracked Charpy-sized specimens in ASTM E1820 (Annex A17). A second proposed change, which originated from a negative submitted during the previous ballot of E636 in 2012, is the recommendation to precrack fracture toughness after irradiation rather than before irradiation (as recommended in the current version). The increase in yield strength induced by irradiation should also be taken into account when establishing the precracking conditions.


    fracture toughness; irradiation; notch ductility; nuclear reactor vessels; surveillance (of nuclear reactor vessels)
    ; Irradiance/irradiation; Neutron flux/fluence; Nuclear reactor vessels--surveillance; Radiation exposure--nuclear materials/applications;
    Citing ASTM Standards
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    Work Item Status

    Date Initiated:

    Technical Contact:
    Enrico Lucon

    Draft Under Development