ACCUMULATION OF RADIATION DAMAGE IN ZIRCONIUM ALLOYS Zr-1 AND Zr-4 UNDER IRRADIATION WITH 300 keV HEAVY IONS

Experiments were carried out to induce radiation defects in zirconium alloys for fuel elements Zr-1 and Zr-4 using accelerated heavy ion beams. The required irradiation dose was delivered using 300 keV Fe2+ and Zr2+ ions with an ion implanter in the Institute of Applied Physics of the National Academy of Sciences of Ukraine. These ion types were selected as the most relevant for the irradiation of structural materials due to their elemental composition. The results were analyzed using the PIXE method to assess the elemental concentration profiles in the surface layer of the alloys, and by TEM microscopy to study the effects of irradiation at doses of 5, 50, and 100 dpa at different substrate heating temperatures of 250, 350, and 500 °C.

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Publication Details

Published
2025-06-27
DOI
https://doi.org/10.46813/2025-157-186
Primary Topic
Nuclear Materials and Properties
Type
article
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article

ACCUMULATION OF RADIATION DAMAGE IN ZIRCONIUM ALLOYS Zr-1 AND Zr-4 UNDER IRRADIATION WITH 300 keV HEAVY IONS

V. M. Bilyk, O.Yu. Karpenko, O.Yu. Roenko, V.A. Baturin et al.
Nuclear Materials and Properties
article

ACCUMULATION OF RADIATION DAMAGE IN ZIRCONIUM ALLOYS Zr-1 AND Zr-4 UNDER IRRADIATION WITH 300 keV HEAVY IONS

V. M. Bilyk, O.Yu. Karpenko, O.Yu. Roenko, V.A. Baturin, M.I. Danylenko, P. O. Litvinov, S.O. Yeryomin
article en

Abstract

Experiments were carried out to induce radiation defects in zirconium alloys for fuel elements Zr-1 and Zr-4 using accelerated heavy ion beams. The required irradiation dose was delivered using 300 keV Fe2+ and Zr2+ ions with an ion implanter in the Institute of Applied Physics of the National Academy of Sciences of Ukraine. These ion types were selected as the most relevant for the irradiation of structural materials due to their elemental composition. The results were analyzed using the PIXE method to assess the elemental concentration profiles in the surface layer of the alloys, and by TEM microscopy to study the effects of irradiation at doses of 5, 50, and 100 dpa at different substrate heating temperatures of 250, 350, and 500 °C.

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Nuclear Materials and Properties
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