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    STP611

    Displacement Spike Annealing in Iron at Reactor Temperatures

    Published: 01 January 1976


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    Abstract

    Displacement spike annealing computer experiments were done for body-centered cubic (bcc) and face-centered cubic (fcc) iron using five different annealing models. Each model predicted a greater number of free interstitials than free vacancies. The number of annihilation events was increased by an increase in cluster migration and decreased by an increase in the clustering interaction radius. The largest number of surviving defects occurred when clusters of four or more defects were immobile and a small clustering interaction radius was assigned.

    Keywords:

    radiation, displacement spikes, defect annealing, computer experiments, irradiation, irradiation hardening, radiation effects, damage units, damage saturation, steel, nuclear reactor materials, precipitation


    Author Information:

    Beeler, JR
    Professor, Materials Engineering and Nuclear Engineering, and research assistant, North Carolina State University, Raleigh, N.C.

    Beeler, MF
    Professor, Materials Engineering and Nuclear Engineering, and research assistant, North Carolina State University, Raleigh, N.C.


    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP38065S