Nanostructured NiCoFeCr alloy with superior high-temperature irradiation resistance

Abstract The current research utilized a unique material design of nanostructured medium-entropy alloys with numerous defect sinks, offering great potential to withstand extreme conditions in advanced nuclear reactors. Hence, this work examined oxide dispersion strengthened (ODS)-NiCoFeCr alloy with nanosized grains after Ni +2 irradiation at 580 °C up to a peak damage of 101 displacements per atom. The alloy showed insignificant hardening and no detectable void formation following irradiation. Also, oxide nanoprecipitates and grains exhibited a limited growth of ~2 and ~5 nm, respectively, with irradiation. The volume-averaged dislocation length density remained on the order of ~10 14 m −2 , and the mean dislocation length showed a slight increase from 89 to 97 nm, with irradiation. A lower level of radiation-induced segregation was observed at the grain boundaries; however, the extent of RIS depended on the misorientation angles, with a maximum at 45.7° among the grain boundaries analyzed.

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Publication Details

Journal
npj Materials Degradation
Published
2025-07-24
DOI
https://doi.org/10.1038/s41529-025-00642-2
Citations
1
Primary Topic
High Entropy Alloys Studies
Type
article
Field-Weighted Citation Impact
0.71

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article

Nanostructured NiCoFeCr alloy with superior high-temperature irradiation resistance

Mingyang Li, K. Mulewska, Witold Chromiński, Ruben Bjørge et al.
1 citations
npj Materials Degradation
High Entropy Alloys Studies
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article

Nanostructured NiCoFeCr alloy with superior high-temperature irradiation resistance

Mingyang Li, K. Mulewska, Witold Chromiński, Ruben Bjørge, Ł. Kurpaska, Pedro A. Ferreirós, Randi Holmestad, Per Erik Vullum, Damian Kalita, Sri Tapaswi Nori, Yanwen Zhang, Yongqin Chang
article en
1 citations

Abstract

Abstract The current research utilized a unique material design of nanostructured medium-entropy alloys with numerous defect sinks, offering great potential to withstand extreme conditions in advanced nuclear reactors. Hence, this work examined oxide dispersion strengthened (ODS)-NiCoFeCr alloy with nanosized grains after Ni +2 irradiation at 580 °C up to a peak damage of 101 displacements per atom. The alloy showed insignificant hardening and no detectable void formation following irradiation. Also, oxide nanoprecipitates and grains exhibited a limited growth of ~2 and ~5 nm, respectively, with irradiation. The volume-averaged dislocation length density remained on the order of ~10 14 m −2 , and the mean dislocation length showed a slight increase from 89 to 97 nm, with irradiation. A lower level of radiation-induced segregation was observed at the grain boundaries; however, the extent of RIS depended on the misorientation angles, with a maximum at 45.7° among the grain boundaries analyzed.

npj Materials DegradationVol. 9(1)
Warsaw University of Technology (PL), SINTEF (NO), Queen's University (CA), Norwegian University of Science and Technology (NO), National Centre for Nuclear Research (PL), SINTEF Industry (NO), University of Tennessee at Knoxville (US), VTT Technical Research Centre of Finland (FI), University of Science and Technology Beijing (CN)
European Commission, Fundacja na rzecz Nauki Polskiej, Canada Excellence Research Chairs, Government of Canada, Horizon 2020, European Regional Development Fund
Openalex Percentile: Top 30%
High Entropy Alloys Studies
0.71
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