Study of radiation damage in nuclear materials by positron lifetime spectroscopy

ORAL

Abstract

Microstructure of four different oxide-dispersion-strengthened (ODS) steels (KAERI-A, B, C, D) with 12{\%} chromium content was studied in term of vacancy defects presence and their accumulation due to irradiation. Radiation damage was simulated by implantation of $^{2+}$He ions via a linear accelerator at the Laboratory of ion beams of the Slovak University of Technology. A second set of samples was irradiated by neutrons in Washington State University Nuclear Radiation Center. A comparison of simulated damage by $^{2+}$He and damage dealt by real reactor environment was evaluated by positron lifetime measurements in emphasis on defect accumulation.

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Authors

  • Iveta Barto\v{s}ov\'a

    • Institute of Nuclear and Physical Engineering, Slovak University of Technology in Bratislava, Ilkovi\v{c}ova 3, 812 19 Bratislava, Slovak Republic

  • Amine Bouhaddane

    • Institute of Nuclear and Physical Engineering, Slovak University of Technology in Bratislava, Ilkovi\v{c}ova 3, 812 19 Bratislava, Slovak Republic

  • Vladim\'Ir Sluge

    • Institute of Nuclear and Physical Engineering, Slovak University of Technology in Bratislava, Ilkovi\v{c}ova 3, 812 19 Bratislava, Slovak Republic

  • Donald Wall

    • Nuclear Radiation Center, PO Box 641300, Washington State University, Pullman, WA 99164-1300, USA

  • Farida Selim

    • Department of Physics, Bowling Green State University, 104 Overman Hall, OH 43403, USA