Abstract
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.
| Original language | English |
|---|---|
| Article number | 153643 |
| Journal | Journal of Nuclear Materials |
| Volume | 563 |
| DOIs | |
| State | Published - May 2022 |
Funding
This work was performed using funding received from the U.S. Department of Energy , Office of Nuclear Energy under Contract No. DE-AC05-00OR22725 with UT-Battelle, LLC. The XRD analysis was performed at the Joint Institute for Advanced Materials (JIAM) Diffraction Facility and the ion irradiations were performed at the Ion Beam Materials Laboratory (IBML). Both user centers are located at the University of Tennessee, Knoxville. The TEM analysis was performed at the Low Activation Materials Development and Analysis (LAMDA) facility at Oak Ridge National Laboratory. This work was performed using funding received from the U.S. Department of Energy, Office of Nuclear Energy under Contract No. DE-AC05-00OR22725 with UT-Battelle, LLC. The XRD analysis was performed at the Joint Institute for Advanced Materials (JIAM) Diffraction Facility and the ion irradiations were performed at the Ion Beam Materials Laboratory (IBML). Both user centers are located at the University of Tennessee, Knoxville. The TEM analysis was performed at the Low Activation Materials Development and Analysis (LAMDA) facility at Oak Ridge National Laboratory.
Keywords
- Coated particle fuel
- Inert matrix fuel
- Si3N4
- Space nuclear propulsion
- ZrN