Uranium nitride-silicide advanced nuclear fuel: higher efficiency and greater safety

Tashiema L. Wilson, Emily E. Moore, Denise Adorno Lopes, Vancho Kocevski, Elizabeth Sooby Wood, Joshua T. White, Andrew T. Nelson, Jacob W. McMurray, Simon C. Middleburg, Peng Xu, Theodore M. Besmann

Research output: Contribution to journalArticlepeer-review

28 Scopus citations

Abstract

As part of Accident Tolerant Fuel initiative for light water reactors, uranium silicide and silicide-nitride are being considered as fuels that can be combined with a more robust cladding such as a ferritic (FeCrAl) alloy. Although these materials have been studied in the past, uncertainties remain concerning the fundamental behaviour of these systems. In this study, four compositions between U3Si5 and USi2 were fabricated by arc-melting. Additionally, in an effort to understand the UN–U3Si2 fuel system, an unidentified U–Si–N ternary was observed in samples fabricated by arc-melting U3Si2 in the presence of varied concentrations of N2 in Ar. The analyses of compositions prepared to investigate these systems include structural characterisation using X-ray diffraction and compositional analysis employing scanning electron microscopy with energy dispersive spectrometry. Initial values of the Gibbs energy parameters via the CALPHAD (CALculation of PHAse Diagrams) method have been developed for the ternary phases observed upon U3Si2–FeCrAl interactions.

Original languageEnglish
Pages (from-to)s76-s81
JournalAdvances in Applied Ceramics
Volume117
Issue numbersup1
DOIs
StatePublished - Oct 17 2018

Funding

This research is being performed using funding received from the DOE Office of Nuclear Energy’s Nuclear Energy University Programs [grant number DE-NE0008570]. One of the authors, T. L. Wilson, was supported by a U. S. Nuclear Regulatory Commission Fellowship. This paper was originally presented at the Ultra-High Temperature Ceramics: Materials for Extreme Environments Applications IV Conference (Windsor, UK) and has subsequently been revised and extended before consideration by Advances in Applied Ceramics. This research is being performed using funding received from the DOE Office of Nuclear Energy’s Nuclear Energy University Programs [grant number DE-NE0008570]. One of the authors, T. L. Wilson, was supported by a U. S. Nuclear Regulatory Commission Fellowship.

FundersFunder number
DOE Office of Nuclear Energy
Nuclear Energy University Programs
U.S. Nuclear Regulatory Commission
Fuel Cycle Technologies
Nuclear Energy University ProgramDE-NE0008570

    Keywords

    • Advanced nuclear fuel
    • ferritic alloy
    • uranium nitride
    • uranium silicide
    • uranium silicide-nitride

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