April 7 - 11, 2025
Seattle, Washington
Symposium Supporters
2025 MRS Spring Meeting & Exhibit
EN03.11.05

Thermal Oxidation and High Temperature Structures of Uranium Carbide—New Insights into the U-C-O System from In Situ X-Ray Diffraction Studies

When and Where

Apr 10, 2025
4:45pm - 5:00pm
Summit, Level 3, Room 339

Presenter(s)

Co-Author(s)

Xiaofeng Guo1,Emma Kindall1,Natalie Yaw1,Juejing Liu1,Chris Malin Dixon Wilkins1,Sam Karcher1,Bryn Merrill1,Zi-Kui Liu2,Hongwu Xu3,4,John McCloy1,Arjen van Veelen3,Joshua White3

Washington State University1,The Pennsylvania State University2,Los Alamos National Laboratory3,Arizona State University4

Abstract

Xiaofeng Guo1,Emma Kindall1,Natalie Yaw1,Juejing Liu1,Chris Malin Dixon Wilkins1,Sam Karcher1,Bryn Merrill1,Zi-Kui Liu2,Hongwu Xu3,4,John McCloy1,Arjen van Veelen3,Joshua White3

Washington State University1,The Pennsylvania State University2,Los Alamos National Laboratory3,Arizona State University4
Uranium carbide (UC) shares a number of characteristics with industry standard uranium oxide, that make both ceramics well-suited to nuclear fuel applications, including high melting points and high tolerance to irradiation. In addition to this, UC, along with other non-oxide ceramic fuel candidates, boasts higher thermal conductivity and higher fissile density than conventional uranium oxide fuels, making it a strong candidate for use in emerging Generation IV advanced reactors as both a pristine fuel and a component in accident tolerant TRISO fuels. For fuel qualification, it is critical to evaluate thermal oxidation behavior, phase changes and thermodynamics of UC under normal and off-normal reactor conditions. A rigorous understanding of U-C-O phase equilibria is also a requisite for assessing possible disposal routes, where oxidation to less reactive oxides is widely considered the necessary first step prior to storage. In this work, UC was characterized with in situ high temperature synchrotron x-ray diffraction under low and 0.21 atm O2 partial pressure conditions, with temperatures up to 960 K and 770 K respectively.

Among the two in situ studies, we were able to determine the temperature dependent thermal expansion function of UC from room temperature to 960 K from the low oxygen partial pressure conditions. The mean coefficient of thermal expansion at 960 K was found to be 11.5 ● 10-6 K-1, in good agreement with previously reported values. Of particular interest in this experiment was the observed formation of the tetragonal I4/mmm α-UC2 phase around 800 K. Thermodynamically α-UC2 is not favored to form at this temperature but may be stabilized as oxygen substituted UC2-xOx under low O2 conditions. Until now the lower temperature boundary of the region of stability for this phase has not been identified. Herein, from its observed formation at 800 K, we report a CALPHAD optimized Gibbs molar energy for the α-UC2-xOx phase. Furthermore, the second experiment conducted in open-air provided a clear bulk thermal oxdiation pathway of UC: UC → UO2 → U3O8, which was confirmed by reitveld refinement of diffraction patterns.

New insights and discoveries from this work emphasizes the incomplete nature of our understanding of U-C-O phase equilbria, highlighting the importance of continued investigation into this critical system for the deployment of fuels in advanced reactors both during operation and for permanent spent fuel disposal.

Keywords

nuclear materials | thermodynamics | x-ray diffraction (XRD)

Symposium Organizers

Marjorie Bertolus, Commissariat à l’énergie atomique et aux énergies alternatives
Michael Cooper, Los Alamos National Laboratory
David Frazer, General Atomics
Fabiola Cappia, Idaho National Laboratory

Session Chairs

Kevin Field
Par Olsson

In this Session