Nanostructured NiCoFeCr alloy with superior high-temperature irradiation resistance

Sri Tapaswi Nori; Pedro A. Ferreirós; Damian Kalita; Ruben Bjørge; Per Erik Vullum; Katarzyna Mulewska; Witold Chrominski; Mingyang Li; Yongqin Chang; Yanwen Zhang; Randi Holmestad; Lukasz Kurpaska

doi:10.1038/s41529-025-00642-2

Nanostructured NiCoFeCr alloy with superior high-temperature irradiation resistance

Sri Tapaswi Nori^*
, Pedro A. Ferreirós
, Damian Kalita
, Ruben Bjørge
, Per Erik Vullum
, Katarzyna Mulewska
, Witold Chrominski
, Mingyang Li
, Yongqin Chang
, Yanwen Zhang
, Randi Holmestad
, Lukasz Kurpaska

^*Corresponding author for this work

BA4509 Advanced materials for nuclear energy

Research output: Contribution to journal › Article › Scientific › peer-review

1 Citation (Scopus)

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 ~10¹⁴ 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.

Original language	English
Article number	91
Journal	npj Materials degradation
Volume	9
Issue number	1
DOIs	https://doi.org/10.1038/s41529-025-00642-2
Publication status	Published - Dec 2025
MoE publication type	A1 Journal article-refereed

Funding

This research was funded by the European Union Horizon 2020 research and innovation program under Grant Agreement No. 857470 and from the European Regional Development Fund via Foundation for Polish Science International Research Agenda PLUS program Grant No. MAB PLUS/2018/8 and the initiative of the Ministry of Science and Higher Education “Support for the activities of Centers of Excellence established in Poland under the Horizon 2020 program” under agreement No. MEiN/2023/DIR/3795. This project has received funding from the European Union's Horizon 2020 research and innovation program under grant agreement No. 823717—ESTEEM3. This project has received funding from the European Union's Horizon 2020 EURATOM Programme under grant agreement No. 10106008 via the OFFERR project. Y.Z. is supported through the CANADA EXCELLENCE RESEARCH CHAIRS (CERC) program.

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10.1038/s41529-025-00642-2Licence: CC BY

Cite this

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title = "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 \textasciitilde{}2 and \textasciitilde{}5 nm, respectively, with irradiation. The volume-averaged dislocation length density remained on the order of \textasciitilde{}1014 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.",

author = "Nori, \{Sri Tapaswi\} and Ferreir{\'o}s, \{Pedro A.\} and Damian Kalita and Ruben Bj{\o}rge and Vullum, \{Per Erik\} and Katarzyna Mulewska and Witold Chrominski and Mingyang Li and Yongqin Chang and Yanwen Zhang and Randi Holmestad and Lukasz Kurpaska",

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doi = "10.1038/s41529-025-00642-2",

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AU - Nori, Sri Tapaswi

AU - Ferreirós, Pedro A.

AU - Kalita, Damian

AU - Bjørge, Ruben

AU - Vullum, Per Erik

AU - Mulewska, Katarzyna

AU - Chrominski, Witold

AU - Li, Mingyang

AU - Chang, Yongqin

AU - Zhang, Yanwen

AU - Holmestad, Randi

AU - Kurpaska, Lukasz

PY - 2025/12

Y1 - 2025/12

N2 - 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 ~1014 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.

AB - 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 ~1014 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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VL - 9

JO - npj Materials degradation

JF - npj Materials degradation

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ER -

Nanostructured NiCoFeCr alloy with superior high-temperature irradiation resistance

Abstract

Funding

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OFFERR: eurOpean platForm For accEssing nucleaR R&d facilities

NOMATEN: Centre of Excellence in Multifunctional Materials for Industrial and Medical Applications

Cite this

Nanostructured NiCoFeCr alloy with superior high-temperature irradiation resistance

Abstract

Funding

Access to Document

Other files and links

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Projects

OFFERR: eurOpean platForm For accEssing nucleaR R&d facilities

NOMATEN: Centre of Excellence in Multifunctional Materials for Industrial and Medical Applications

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