Embrittlement of chromium alloys after neutron irradiation at high temperatures to damage doses of 10–46 dpa

IF 2.3 2区 物理与天体物理 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Materials and Energy Pub Date : 2025-01-08 DOI:10.1016/j.nme.2025.101871
Vladimir Chakin , Ramil Gaisin , Carsten Bonnekoh , Michael Duerrschnabel , Michael Rieth , Bronislava Gorr , Mikola Brodnikikovsky , Mikola Krapivka , Sergey Firstov
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Abstract

The study of chromium alloys, including the low-alloyed BX-2 K alloy and Cr-Fe alloys alloyed with Zr, Y, Al, Mn, Mo additions, after irradiation at temperatures ranging from 400 to 1000 °C and neutron fluences of (2.0 − 9.3) × 1026 m−2 (E > 0.1 MeV), corresponding to damage doses of 10–46 dpa, revealed a significant tendency for radiation embrittlement in all studied alloys. The tensile ductile-to-brittle transition temperature (DBTT) for these alloys increased to 250–700 °C after irradiation, while the initial DBTT was lower than room temperature. To enhance radiation embrittlement resistance, the Cr10FeZrY alloy, which exhibits a minimum DBTT of 250 °C, is recommended as a basis for further improvement of mechanical properties of Cr-Fe alloys under neutron irradiation.
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来源期刊
Nuclear Materials and Energy
Nuclear Materials and Energy Materials Science-Materials Science (miscellaneous)
CiteScore
3.70
自引率
15.40%
发文量
175
审稿时长
20 weeks
期刊介绍: The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. Nuclear Materials and Energy publishes original research articles of up to 6 pages in length.
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