Published April 2021 | Version v1
Journal article

Phase and defect evolution in uranium-nitrogen-oxygen system under irradiation

  • 1. Idaho National Laboratory, Idaho Falls, ID 83415 (United States)
  • 2. The Ohio State University, Columbus, OH 43210 (United States)
  • 3. Dutch Institute for Fundamental Energy Research, 5612 AJ Eindhoven (Netherlands)
  • 4. University of Wisconsin-Madison, Madison, WI 53706 (United States)
  • 5. Boise State University, Boise, ID 83725 (United States)

Description

Uranium mononitride (UN) with 5 wt.% uranium dioxide (UO2) is used as a model system to study the phase and defect evolution under proton irradiation in nitride-oxide composite. Phase composition, crystallographic orientation relationships (ORs) and dislocation loops were characterized using X-ray diffraction, transmission electron microscopy, and energy dispersive X-ray spectroscopy techniques. Proton-irradiation at elevated temperatures promoted the transformation of UN into uranium sesquinitride (U2N3) and UO2 phases. U2N3 and UO2 formed a fully coherent structure with two ORs: {002}U2N3‖{002}UO2 and [001]U2N3‖[001]UO2; U2N3{101}‖UO2{101} and U2N3[101]‖UO2[101] due to low lattice misfit (2.3%) and low interfacial energy (127 mJ/m2). Observed oxidation of UN and coherent interface are consistent with density-functional theory calculations which suggest lower energy for oxidized configuration and low energy of the interface. The dislocation loops grew while their number density decreased with the temperature and dose. The loop size was over three times larger in two nitride phases than that in UO2, while the number density was one order of magnitude higher in UO2 than in nitride phases. Loop density and diameter were analyzed using a kinetic rate theory that considers stoichiometric loop evolution. This analysis led to the conclusion in all compounds loop growth is governed by mobility of uranium interstitials, and enabled measurement of diffusion coefficients of uranium interstitials and non-metal interstitials and vacancies. This analysis provided a comparative study of early stage of microstructure evolution under irradiation which has implications for use of this mixture as advanced fuel in nuclear energy systems.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.actamat.2021.116778

Additional details

Identifiers

DOI
10.1016/j.actamat.2021.116778;
PII
S1359645421001580;

Publishing Information

Journal Title
Acta Materialia
Journal Volume
208
Journal Page Range
vp.
ISSN
1359-6454
CODEN
ACMAFD

Optional Information

Copyright
Copyright (c) 2021 Acta Materialia Inc. Published by Elsevier Ltd. All rights reserved.