Adrien J. Terricabras, Ling Wang, Alicia M. Raftery, Andrew T. Nelson, Steven J. Zinkle

Silicon nitride and zirconium nitride have been proposed as potential materials for multiple nuclear applications (inert matrix fuels, accident tolerant fuels, space nuclear power, fusion reactor design), yet knowledge on their behavior under irradiation remains limited. Ion irradiations were perfor...

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Veröffentlicht in:Journal of nuclear materials 2022-05, Vol.563, p.1
Hauptverfasser: Terricabras, Adrien J, Wang, Ling, Raftery, Alicia M, Nelson, Andrew T, Zinkle, Steven J
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Nelson, Andrew T
Zinkle, Steven J
description Silicon nitride and zirconium nitride have been proposed as potential materials for multiple nuclear applications (inert matrix fuels, accident tolerant fuels, space nuclear power, fusion reactor design), yet knowledge on their behavior under irradiation remains limited. Ion irradiations were performed using 15 MeV Ni5+ ions on Si3N4 and ZrN samples, with midrange doses (around 3 µm) from 1 to 50 dpa and temperatures from 300 to 700℃. Volumetric lattice swelling was determined by grazing incidence X-ray diffraction, defect production and evolution were tracked using Transmission Electron Microscopy, and nanoindentation was performed to quantify the ceramics' mechanical properties evolution. The results from these irradiation studies on nitride ceramics help fill the current gap present in the literature. Behavior consistent with past work on irradiated Si3N4 was observed with respect to mechanical properties and defect formation up to 15 dpa and 500°C. Failure of the grain boundary sintering aid in Si3N4 was observed above these conditions. Different behavior was observed in both nitrides at 50 dpa and 700°C, where lattice swelling increased past potential saturation values. Unreported cavity formation was witnessed in both materials under all irradiation conditions, with stable number density and slight size increase above 15 dpa. The mechanism for the cavity formation remains to be determined.
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Volumetric lattice swelling was determined by grazing incidence X-ray diffraction, defect production and evolution were tracked using Transmission Electron Microscopy, and nanoindentation was performed to quantify the ceramics' mechanical properties evolution. The results from these irradiation studies on nitride ceramics help fill the current gap present in the literature. Behavior consistent with past work on irradiated Si3N4 was observed with respect to mechanical properties and defect formation up to 15 dpa and 500°C. Failure of the grain boundary sintering aid in Si3N4 was observed above these conditions. Different behavior was observed in both nitrides at 50 dpa and 700°C, where lattice swelling increased past potential saturation values. Unreported cavity formation was witnessed in both materials under all irradiation conditions, with stable number density and slight size increase above 15 dpa. 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subjects Ceramics
Evolution
Fuels
Grain boundaries
Irradiation
Mechanical properties
Nanoindentation
Nuclear accidents & safety
Nuclear energy
Nuclear fuels
Nuclear fusion
Reactor design
Silicon nitride
Sintering aids
Swelling
Transmission electron microscopy
X-ray diffraction
Zirconium
Zirconium nitrides
title Adrien J. Terricabras, Ling Wang, Alicia M. Raftery, Andrew T. Nelson, Steven J. Zinkle
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