Novel effects of grain size and ion implantation on grain boundary segregation in ion irradiated austenitic steel

Hoffman, Andrew K.; Zhang, Yongfeng; Arivu, Maalavan; He, Li; Sridharan, Kumar; Wu, Yaqiao; Islamgaliev, Rinat K.; Valiev, Ruslan Z.; Wen, Haiming

doi:10.1016/j.actamat.2023.118714

Novel effects of grain size and ion implantation on grain boundary segregation in ion irradiated austenitic steel

Journal Article · Mon Jan 23 00:00:00 EST 2023 · Acta Materialia

DOI:https://doi.org/10.1016/j.actamat.2023.118714· OSTI ID:2418297

Hoffman, Andrew K. ^[1]; Zhang, Yongfeng ^[2]; ^[1]; He, Li ^[2]; Sridharan, Kumar ^[2]; Wu, Yaqiao ^[3]; Islamgaliev, Rinat K. ^[4]; Valiev, Ruslan Z. ^[4]; ^[1]

Missouri Univ. of Science and Technology, Rolla, MO (United States)
Univ. of Wisconsin, Madison, WI (United States)
Boise State Univ., ID (United States); Center for Advanced Energy Studies, Idaho Falls, ID (United States)
Univ. of Science and Technology, Ufa (Russian Federation)

Nuclear reactor environments are extreme in nature due to the combination of exposure to corrosive coolant, mechanical stresses, and neutron irradiation damage. This combination of environments can lead to irradiation induced/assisted precipitation, segregation, and embrittlement coupled with enhanced creep and stress corrosion cracking. While nanostructured materials are of interest in a variety of applications due to their unique properties including high mechanical strength, for nuclear applications nanostructured materials have the added benefit of irradiation resistance due to the high volume density of sinks for irradiation-induced defects. In this study, we show unique radiation-induced segregation (RIS) behavior in nanocrystalline 304 stainless steel (SS304). Typical RIS in austenitic steels includes Ni enrichment and Cr depletion within the grain boundaries. In nanostructured SS304 this RIS is reduced. Furthermore, interestingly, some grain boundaries in the nanocrystalline SS304 in this study were found to be enriched in Cr after Fe²⁺ ion irradiation at 500 °C up to 50 displacements per atom (dpa). To understand this unique observation, lattice-based atomic kinetic Monte Carlo simulations were performed to investigate the effects of grain size, thermal segregation, as well as injected interstitials (introduced as Fe self-ions). The results indicate that the Cr enrichment at grain boundaries may be caused by combined effects of grain size, self-ion injection and preferential Cr diffusion via the interstitial mechanism. In conclusion, the findings also suggest a possible difference in RIS between ion and neutron irradiations.

View Accepted Manuscript (DOE)

Research Organization:: Idaho State Univ., Pocatello, ID (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: NE0008524

OSTI ID:: 2418297

Journal Information:: Acta Materialia, Vol. 246, Issue C; ISSN 1359-6454

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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36 MATERIALS SCIENCE
radiation-induced segregation
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Novel effects of grain size and ion implantation on grain boundary segregation in ion irradiated austenitic steel

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