STP380

    Effect of Irradiation on Bend Transition Temperatures of Molybdenum- and Columbium-Base Alloys

    Published: Jan 1965


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    Abstract

    Because of the potential use of refractory metals as structural materials in nuclear reactors, it is necessary that the influence of irradiation on the ductility of these materials be evaluated. The present study is concerned with the development of suitable test equipment for evaluating the ductile-to-brittle transition temperature of irradiated specimens and with the use of this equipment to evaluate the ductile-to-brittle temperature for several irradiated specimens. The equipment developed for this purpose fits in a standard tensile machine and is capable of remote operation over the temperature range of - 73 to 261 C. The materials studied after irradiation to a neutron dosage of the order of 1020 nvt (>1 Mev) include Mo-0.5Ti, Cb-1Zr, welded Cb-1Zr, and D-43 (10W-1Zr-0.1C). The variables studied were: (1) the metallurgical state of the material prior to irradiation, (2) irradiation dose, and (3) post-irradiation annealing. The transition temperature of the Mo-0.5Ti was determined on the basis of the deflection of the material prior to fracture. The behavior of the Cb-lZr and D-43 alloys was analyzed on the basis of the yield strength.


    Author Information:

    McCoy, H. E.
    Metallurgist and group leader, Oak Ridge National Laboratory, Oak Ridge, Tenn.

    Weir, J. R.
    Metallurgist and group leader, Oak Ridge National Laboratory, Oak Ridge, Tenn.


    Paper ID: STP43526S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP43526S


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