STP426

    Properties of Irradiated Materials Needed for the Design of Reactor Vessels. Part I, Water Cooled Reactors

    Published: Jan 1967


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    Abstract

    The paper is intended to convey to the experimentalist a statement of the type of radiation effects data the designer needs for design of water cooled reactor vessels. It lists the materials properties required, the range of environmental variables to be covered in testing, and briefly describes the use of each property in design. It is concluded that the effect of radiation on brittle fracture transition temperature and fatigue resistance are the most important problems to the vessel designer.

    Keywords:

    metals, nuclear reactors, pressure vessels, water cooling, fracture, embrittlement, fatigue (materials)


    Author Information:

    McLaughlin, D. W.
    Senior engineering analystPersonal member ASTM, Mechanical Technology Inc., Latham, N. Y.


    Paper ID: STP41331S

    Committee/Subcommittee: E10.02

    DOI: 10.1520/STP41331S


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