Grain boundary enhanced UN and U3Si2 pellets with improved oxidation resistance

Lahoda, Edward J.; Xu, Peng; Oelrich, Jr., Robert L.; Shah, Hemant; Wright, Jonathan; Cai, Lu

Grain boundary enhanced UN and U3Si2 pellets with improved oxidation resistance

Patent · 12 October 2021

OSTI ID:1859948

Lahoda, Edward J.; Xu, Peng; Oelrich, Jr., Robert L.; Shah, Hemant; Wright, Jonathan; Cai, Lu

A method of forming a water resistant boundary on a fissile material for use in a water cooled nuclear reactor is described. The method comprises mixing a powdered fissile material selected from the group consisting of UN and U₃Si₂ with an additive selected from oxidation resistant materials having a melting or softening point lower than the sintering temperature of the fissile material, pressing the mixed fissile and additive materials into a pellet, sintering the pellet to a temperature greater than the melting point of the additive. Alternatively, if the melting point of the oxidation resistant particles is greater than the sintering temperature of UN or U₃Si₂, then the oxidation resistant particles can have a particle size distribution less than that of the UN or U₃Si₂.

Research Organization:: Westinghouse Electric Co. LLC, Cranberry Township, PA (United States)

Sponsoring Organization:: USDOE

DOE Contract Number:: NE0008222

Assignee:: Westinghouse Electric Company LLC (Cranberry Township, PA)

Patent Number(s):: 11,145,425

Application Number:: 16/260,889

OSTI ID:: 1859948

Country of Publication:: United States

Language:: English

References (7)

U3Si2 behavior in H2O environments: Part II, pressurized water with controlled redox chemistry Nelson, A. T.; Migdisov, A.; Wood, E. Sooby Journal of Nuclear Materials, Vol. 500 https://doi.org/10.1016/j.jnucmat.2017.12.026	journal	March 2018
U3Si2 behavior in H2O: Part I, flowing steam and the effect of hydrogen Wood, E. Sooby; White, J. T.; Grote, C. J. Journal of Nuclear Materials, Vol. 501 https://doi.org/10.1016/j.jnucmat.2018.01.002	journal	April 2018
Oxidation behavior of U-Si compounds in air from 25 to 1000 C Sooby Wood, E.; White, J. T.; Nelson, A. T. Journal of Nuclear Materials, Vol. 484 https://doi.org/10.1016/j.jnucmat.2016.12.016	journal	February 2017
Kinetics of the oxidation of UN and U(CO) in carbon dioxide, steam and water at elevated temperatures Antill, J. E.; Myatt, B. L. Corrosion Science, Vol. 6, Issue 1 https://doi.org/10.1016/S0010-938X(66)80046-X	journal	January 1966
Review: liquid phase sintering German, Randall M.; Suri, Pavan; Park, Seong Jin Journal of Materials Science, Vol. 44, Issue 1 https://doi.org/10.1007/s10853-008-3008-0	journal	January 2009
Degradation of UN and UN–U ₃ Si ₂ pellets in steam environment Lopes, Denise Adorno; Uygur, Selim; Johnson, Kyle Journal of Nuclear Science and Technology, Vol. 54, Issue 4 https://doi.org/10.1080/00223131.2016.1274689	journal	January 2017
Hydrolysis of uranium mononitride Dell, R. M.; Wheeler, V. J.; Bridger, N. J. Transactions of the Faraday Society, Vol. 63 https://doi.org/10.1039/tf9676301286	journal	January 1967

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