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Nanostructured NiCoFeCr alloy with superior high-temperature irradiation resistance.

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Název: Nanostructured NiCoFeCr alloy with superior high-temperature irradiation resistance.
Autoři: Nori, Sri Tapaswi, Ferreirós, Pedro A., Kalita, Damian, Bjørge, Ruben, Vullum, Per Erik, Mulewska, Katarzyna, Chrominski, Witold, Li, Mingyang, Chang, Yongqin, Zhang, Yanwen, Holmestad, Randi, Kurpaska, Lukasz
Zdroj: NPJ Materials Degradation; 7/24/2025, Vol. 9 Issue 1, p1-11, 11p
Témata: IRRADIATION, RADIATION damage, NANOPARTICLES, NANOSTRUCTURED materials, DISPERSION strengthening, HIGH temperatures, HIGH-entropy alloys
Abstrakt: 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. [ABSTRACT FROM AUTHOR]
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Databáze: Complementary Index
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Abstrakt: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<sup>+2</sup> 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<sup>14</sup> m<sup>−2</sup>, 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. [ABSTRACT FROM AUTHOR]
ISSN:23972106
DOI:10.1038/s41529-025-00642-2