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Title: Ambient melting behavior of stoichiometric uranium oxides

Journal Article · · Frontiers in Nuclear Engineering

As UO 2 is easily oxidized during the nuclear fuel cycle it is important to have a detailed understanding of the structures and properties of the oxidation products. Experimental work over the years has revealed many stable uranium oxides including UO 2 , U 4 O 9 (UO 2.25 ), U 3 O 7 (UO 2.33 ), U 2 O 5 (UO 2.5 ), U 3 O 8 (UO 2.67 ), and UO 3 , all with a number of different polymorphs. These oxides are broadly split into two categories, fluorite-based structures with stoichiometries in the range of UO 2 to UO 2.5 and less dense layered-type structures with stoichiometries in the range of UO 2.5 to UO 3 . While UO 2 is well characterized, both experimentally and computationally, there is a paucity of data concerning higher stoichiometry oxides in the literature. In this work we determine the ambient melting points of all the six stoichiometric uranium oxides listed above and compare them to the available experimental and/or theoretical data. We demonstrate that a family of the six ambient melting points map out a solid-liquid transition boundary consistent with the high-temperature portion of the phase diagram of uranium-oxygen system suggested by Babelot et al.

Sponsoring Organization:
USDOE
OSTI ID:
2274990
Journal Information:
Frontiers in Nuclear Engineering, Journal Name: Frontiers in Nuclear Engineering Vol. 2; ISSN 2813-3412
Publisher:
Frontiers Media SACopyright Statement
Country of Publication:
Switzerland
Language:
English

References (23)

Design Parameters for a Natural Uranium UO3 or U3O8 Fueled Nuclear Reactor report November 2002
A mechanism for the UO2 to α-U3O8 phase transformation journal June 1995
High-temperature X-ray study of uranium oxides in the UO2U3O8 region journal December 1955
Structure and Properties of Some Layered U 2 O 5 Phases: A Density Functional Theory Study journal April 2017
Phonons and thermophysical properties of U1−Pu O2 mixed oxide (MOX) fuels journal August 2020
Diffuse transition and melting in fluorite and antifluorite type of compounds. Heat content of potassium sulfide from 298 to 1260.degree.K journal April 1968
Determination of solidus-liquidus temperatures in the uo2 + x system (−0.50<0.20) journal May 1970
Melting of stoichiometric and hyperstoichiometric uranium dioxide journal June 2005
High-temperature studies of UO2 and ThO2 using neutron scattering techniques journal January 1987
Melting behaviour of uranium-americium mixed oxides under different atmospheres journal January 2020
The system U-UO3: Phase diagram and oxygen potential journal January 1986
A detailed study of UO2 to U3O8 oxidation phases and the associated rate-limiting steps journal September 2006
DFT + U investigation of charged point defects and clusters in UO 2 journal July 2014
Electronic Structure Investigation of the Bulk Properties of Uranium–Plutonium Mixed Oxides (U, Pu)O2 journal August 2018
Thermal Expansion and Change in Volume of Uranium Dioxide on Melting journal December 1963
The uranium-oxygen system at high pressure journal October 1970
Advances in the Experimental Determination of the Uranium–Oxygen Phase Diagram at High Temperature journal July 2005
Systematic Analysis of 4 f Core Photoemission Spectra in Actinide Oxides journal January 1991
DFT + U Study of Uranium Dioxide and Plutonium Dioxide with Occupation Matrix Control journal July 2022
Neutron powder profile studies of the gamma uranium trioxide phases journal January 1977
Thermal expansion in UO2 determined by high-energy X-ray diffraction journal October 2016
Investigation of the solid/liquid phase transitions in the U–Pu–O system journal March 2023
Screened hybrid and DFT + U studies of the structural, electronic, and optical properties of U 3 O 8 journal November 2012