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

Chakin, Vladimir 1; Gaisin, Ramil ORCID iD icon 2; Bonnekoh, Carsten ORCID iD icon 2; Duerrschnabel, Michael ORCID iD icon 2; Rieth, Michael ORCID iD icon 2; Gorr, Bronislava 1; Brodnikikovsky, Mikola; Krapivka, Mikola; Firstov, Sergey
1 Karlsruher Institut für Technologie (KIT)
2 Institut für Angewandte Materialien – Angewandte Werkstoffphysik (IAM-AWP), Karlsruher Institut für Technologie (KIT)

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.

Zugehörige Institution(en) am KIT Institut für Angewandte Materialien – Angewandte Werkstoffphysik (IAM-AWP)
Publikationstyp Zeitschriftenaufsatz
Publikationsmonat/-jahr 03.2025
Sprache Englisch
Identifikator ISSN: 2352-1791
KITopen-ID: 1000178179
HGF-Programm 31.13.05 (POF IV, LK 01) Neutron-Resistant Structural Materials
Erschienen in Nuclear Materials and Energy
Verlag Elsevier
Band 42
Seiten Article no: 101871
Schlagwörter Chromium alloy, Radiation embrittlement, Neutron irradiation
Nachgewiesen in Scopus
Dimensions
OpenAlex
Web of Science

Verlagsausgabe §
DOI: 10.5445/IR/1000178179
Veröffentlicht am 17.01.2025
Seitenaufrufe: 36
seit 17.01.2025
Downloads: 27
seit 24.01.2025
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