Thermal expansion and steam oxidation of uranium mononitride analysed via in situ neutron diffraction
File(s)
Author(s)
Type
Journal Article
Abstract
In situ neutron powder diffraction experiments are applied to physical, kinetic, and microstructural characterization of uranium mononitride as a promising light water reactor fuel material. The temperature-variable coefficient of thermal expansion and isotropic Debye Waller factors are obtained by sequential Rietveld refinement over 499–1873 K. Oxidation of a UN pellet (95.2% density) under flow of 11 mg/min D2O is observed to initiate above 623 K and the rate increases by a factor of approximately 10 from 673 to 773 K, with activation energy 50.6 ± 1.3 kJ/mol; uranium oxide is the only solid corrosion product.
Date Issued
2023-03
Date Acceptance
2022-12-20
Citation
Journal of Nuclear Materials, 2023, 575
ISSN
0022-3115
Publisher
Elsevier
Journal / Book Title
Journal of Nuclear Materials
Volume
575
Copyright Statement
Copyright © Elsevier Ltd. All rights reserved. This manuscript version is made available under the CC-BY-NC-ND 4.0 license https://creativecommons.org/licenses/by-nc-nd/4.0/
Identifier
https://www.webofscience.com/api/gateway?GWVersion=2&SrcApp=PARTNER_APP&SrcAuth=LinksAMR&KeyUT=WOS:000920761900001&DestLinkType=FullRecord&DestApp=ALL_WOS&UsrCustomerID=a2bf6146997ec60c407a63945d4e92bb
Subjects
CONDUCTIVITY
HYDROLYSIS
MATERIAL PROPERTY CORRELATIONS
Materials Science
Materials Science, Multidisciplinary
NITRIDE
Nuclear Science & Technology
PEAK
Science & Technology
Technology
UN
Publication Status
Published
Article Number
154215
Date Publish Online
2022-12-21