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    Irradiation of Some Pressure-Vessel Steels


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    This paper summarizes the results obtained to date in a study of the neutron irradiation behavior of a number of pressure-vessel steels of present and possible future interest. The work was started two years ago in cooperation with Atomic Energy of Canada Limited, and all irradiations have been carried out in the NRX reactor at Chalk River, Ont. The size of the irradiation sample container dictated that subsize impact and tension specimens be used. Also, irradiation temperatures in only the range 120 to 160 F were available. Accepting these limitations, it was thought that a survey of the irradiation-induced changes in properties of several pressure-vessel steels would aid in the search for ferritic steels of enhanced radiation resistance. Also, it was thought that the results might have some applicability for rating the steels in the proper order of radiation resistance for higher temperatures of operation.

    Author Information:

    Trudeau, LP
    International Nickel Co. of Canada Ltd., Toronto, Ont.

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP39592S