Response of 11B enriched ZrB2 ultra-high temperature ceramic to neutron irradiation at elevated temperatures

Lin, Yan-Ru; Koyanagi, Takaaki; Sprouster, David J.; Petrie, Christian M.; Fahrenholtz, William; Hilmas, Greg E.; Katoh, Yutai

doi:10.1016/j.actamat.2024.120111

Response of ¹¹B enriched ZrB₂ ultra-high temperature ceramic to neutron irradiation at elevated temperatures

Journal Article · Fri Jun 14 00:00:00 EDT 2024 · Acta Materialia

DOI:https://doi.org/10.1016/j.actamat.2024.120111· OSTI ID:2376345

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Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
State University of New York, Stony Brook, NY (United States)
Missouri University of Science and Technology, Rolla, MO (United States)

ZrB₂, an ultra-high temperature ceramic (UHTC) is being considered for use in fusion reactor first-wall structures, yet its response to irradiation remains poorly understood. This study employed scanning/transmission electron microscopy (S/TEM), synchrotron X-ray diffraction (XRD), finite element calculations, and thermal property measurements to thoroughly investigate the neutron-irradiation effects on ¹¹B-enriched ZrB₂. Neutron irradiations were conducted at 220 °C and 620 °C, with a neutron fluence of 2.2 × 10²⁵ neutron/m² (energy > 0.1 MeV), resulting in 3.9 dpa and 4200 appm He. The study revealed the unusual prevalence of prism loops and a > c anisotropic lattice swelling, likely linked to the low c/a ratio of ZrB₂, leading to grain boundary microcracking. Reducing the grain sizes was effective in reducing intergranular cracking and macroscopic swelling. The observation of cavities in ZrB₂ irradiated at 620 °C, as opposed to 220 °C, prompts questions about the temperature at which vacancies in ZrB₂ become mobile, and the role of neutron absorption by ¹⁰B in elevating irradiation temperatures. Isotopic enrichment in ¹¹B proves to be a viable strategy for mitigating helium production in transition-metal diborides, which is a critical consideration for nuclear applications. Irradiation-induced defects reduce the thermal diffusivity and conductivity of ZrB₂ by a factor of 4–9, which has important implications for its role as a plasma-facing material in fusion reactors that drive high heat fluxes through first-wall materials. Here, this comprehensive study lays the foundation for understanding ZrB₂ behavior under neutron irradiation and highlights important phenomena to consider for various material applications.

View Accepted Manuscript (DOE)

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Basic Energy Sciences (BES). Scientific User Facilities (SUF); USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: AC05-00OR22725; SC0012704; SC0018322

OSTI ID:: 2376345

Alternate ID(s):: OSTI ID: 2373286

Journal Information:: Acta Materialia, Journal Name: Acta Materialia Vol. 276; ISSN 1359-6454

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Response of ¹¹B enriched ZrB₂ ultra-high temperature ceramic to neutron irradiation at elevated temperatures