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Title: Uranium nitride (UN) pellets with controllable microstructure and phase – fabrication by spark plasma sintering and their thermal-mechanical and oxidation properties

Journal Article · · Journal of Nuclear Materials

Dense uranium mononitride (UN) pellets with controlled microstructures and tailored grain size from large-grained to a few microns are synthesized by spark plasma sintering (SPS) combined with high energy ball milling. The impacts of the sintering conditions on fuel microstructure, grain size, physical density, and phase behavior are systematically investigated, and the thermal-mechanical properties and oxidation behavior of the SPS densified UN pellets are characterized. Higher sintering temperatures and longer ball milling durations and thus finer starting UN powders promote sintering and densification, and dense UN pellets above 95% theoretical density can be achieved by SPS at 1873 K for 10 min. UN phase purity is maintained in the SPS-densified pellets sintered at a lower temperature and short duration. A phase heterogeneity with secondary UO2 or uranium sesquinitride (U2N3) occurs for the UN pellets sintered at higher temperatures using finer UN powders. The hardness and fracture toughness of the SPS-densified UN pellets increase with smaller grain sizes and higher densities to 7.9 GPa and 3.5 MPa m1/2, respectively. Furthermore, both small (1–2 μm) and large grain-sized (30–50 µm) UN pellets exhibit good thermal conductivity. Dynamic oxidation testing by a thermogravimetric analyzer in air shows that the onset temperature for oxidation varies with microstructure and phase heterogeneity of the SPS densified UN pellets. Particularly, the smaller-grained (micron-sized) UN pellets containing uranium oxides and U2N3 display lower weight gain and significantly-reduced oxidation kinetics, and full oxidation completes at a temperature above 1173 K when tested with a ramp rate of 10 K/min.

Research Organization:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
89233218CNA000001; NE0008947; NE0008824
OSTI ID:
1819162
Report Number(s):
LA-UR-21-25305; TRN: US2214609
Journal Information:
Journal of Nuclear Materials, Vol. 557; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (37)

Determining the Kapitza resistance and the thermal conductivity of polycrystals: A simple model journal April 1998
Grain growth in uranium nitride prepared by spark plasma sintering journal May 2018
Thermal Conductivity of Uranium Nitride and Carbide journal September 2014
Microstructure Effects on Fracture Strength of U0 2 Fuel Pellets journal December 1982
Manufacture of fully dense uranium nitride pellets using hydride derived powders with spark plasma sintering journal September 2014
Thermal Conductivity in Nanocrystalline Ceria Thin Films journal December 2013
Fracture properties of sintered UO2 ceramic pellets with duplex microstructure journal June 2007
Spark plasma sintering and porosity studies of uranium nitride journal May 2016
Grain growth and densification of uranium mononitride during spark plasma sintering journal March 2021
Development of an accident-tolerant fuel composite from uranium mononitride (UN) and uranium sesquisilicide (U3 Si2) with increased uranium loading journal April 2016
UN microspheres embedded in UO2 matrix: An innovative accident tolerant fuel journal November 2020
A Critical Evaluation of Indentation Techniques for Measuring Fracture Toughness: I, Direct Crack Measurements journal September 1981
Nano- and micro-indentation testing of sintered UO2 fuel pellets with controlled microstructure and stoichiometry journal April 2019
Spark plasma sintering (SPS) densified U3Si2 pellets: Microstructure control and enhanced mechanical and oxidation properties journal June 2020
The sintering of uranium mononitride journal October 1965
Uranium nitride fuels in superheated steam journal February 2017
Oxidation of uranium mononitride journal September 1975
Material property correlations for uranium mononitride journal May 1990
Temperature and Finite Pulse‐Time Effects in the Flash Method for Measuring Thermal Diffusivity journal July 1963
UO2–UN composites with enhanced uranium density and thermal conductivity journal October 2015
Volatilization characteristics of uranium mononitride journal May 1969
Oxidation behavior of U-Si compounds in air from 25 to 1000 C journal February 2017
Thermophysical and mechanical property assessment of UB2 and UB4 sintered via spark plasma sintering journal March 2020
Thermal conductivity correlation for uranium nitride fuel between 10 and 1923 K journal February 1988
Neutronic performance of uranium nitride composite fuels in a PWR journal August 2014
Technical solutions and development stages for the BREST-OD-300 reactor unit journal October 2012
Uranium nitrides journal September 1963
Effect of titania addition on hot hardness of UO2 journal February 2004
U3Si2 and UO2 composites densified by spark plasma sintering for accident-tolerant fuels journal June 2020
Oxidation of UN/U2N3-UO2 composites: an evaluation of UO2 as an oxidation barrier for the nitride phases journal February 2021
A modified model for hall-petch behavior in nanocrystalline materials journal November 1992
Uranium nitride fuel swelling correlation journal February 1990
Phase and defect evolution in uranium-nitrogen-oxygen system under irradiation journal April 2021
Interfacial thermal resistance in nanocrystalline yttria-stabilized zirconia journal May 2002
30 Years of experience in operating the BN-600 sodium-cooled fast reactor journal August 2010
Synthesis and sintering of UN-UO2 fuel composites journal November 2015
Microscopic origin of lattice contraction and expansion in undoped rutile TiO 2 nanostructures journal May 2014