ASTM E636 - 20

    Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels

    Active Standard ASTM E636 | Developed by Subcommittee: E10.02

    Book of Standards Volume: 12.02

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    Significance and Use

    3.1 Practices E185 and E2215 describe a minimum program for the surveillance of reactor vessel materials, specifically mechanical property changes that occur in service. This guide may be applied to generate additional information on radiation-induced property changes to better assist the determination of the optimum reactor vessel operation schemes.

    1. Scope

    1.1 This guide discusses test procedures that can be used in conjunction with, but not as alternatives to, those required by Practices E185 and E2215 for the surveillance of nuclear reactor vessels. The supplemental mechanical property tests outlined permit the acquisition of additional information on radiation-induced changes in mechanical properties of the reactor vessel steels.

    1.2 This guide provides recommendations for the preparation of test specimens for irradiation, and identifies special precautions and requirements for reactor surveillance operations and post-irradiation test planning. Guidance on data reduction and computational procedures is also given. Reference is made to other ASTM test methods for the physical conduct of specimen tests and for raw data acquisition.

    1.3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

    1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

    2. Referenced Documents (purchase separately) The documents listed below are referenced within the subject standard but are not provided as part of the standard.

    ASME Standards

    ASME Boiler and Pressure Vessel Code, Section III Subsection NB (Class 1 Components)

    ASTM Standards

    E23 Test Methods for Notched Bar Impact Testing of Metallic Materials

    E185 Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels

    E399 Test Method for Linear-Elastic Plane-Strain Fracture Toughness KIc of Metallic Materials

    E1253 Guide for Reconstitution of Irradiated Charpy-Sized Specimens

    E1820 Test Method for Measurement of Fracture Toughness

    E1921 Test Method for Determination of Reference Temperature, To, for Ferritic Steels in the Transition Range

    E2215 Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels

    E2298 Test Method for Instrumented Impact Testing of Metallic Materials

    ICS Code

    ICS Number Code 27.120.10 (Reactor engineering)

    Referencing This Standard
    Link Here
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    DOI: 10.1520/E0636-20

    Citation Format

    ASTM E636-20, Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, ASTM International, West Conshohocken, PA, 2020,

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