Equibiaxial flexural strength determination of UO2 using a ball-on-ring test

Lupercio, Adrianna E.; Doyle, Cayden; Nelson, Andrew T.; Jaques, Brian J.

doi:10.1016/j.jnucmat.2023.154850

Equibiaxial flexural strength determination of UO₂ using a ball-on-ring test

Journal Article · Thu Nov 30 00:00:00 EST 2023 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2023.154850· OSTI ID:2333856

^[1]; Doyle, Cayden ^[1]; ^[2]; ^[1]

Boise State Univ., ID (United States); Center for Advanced Energy Studies, Idaho Falls, ID (United States)
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

To increase nuclear fuel performance and reliability, their mechanical properties require an accurate and statistically relevant assessment. Biaxial flexural strength tests provide an alternative to bend bar techniques for assessing mechanical behavior; namely, the transverse rupture strength (TRS) of ceramic samples. Biaxial test samples require simple geometries and minimal surface preparation, reducing fabrication costs and handling hazards. This study investigated the TRS of polycrystalline UO₂ fuel forms at room temperature using a ball-on-ring test fixture. Here, pellets were fabricated from UO₂ powder using conventional powder processing and sintering techniques. The TRS and Weibull parameters were obtained through Weibull statistics on over 60 UO₂ samples tested under equibiaxial flexure. The larger sample size in this study enabled a more robust Weibull statistical analysis than alternative test methods, which may not capture the stochastic failure of typical ceramics. Furthermore, two different loading ball diameters were employed to assess the impact of contact damage on fracture strength. While Hertzian contact damage was observed with the smaller loading ball, the fracture strength remained unaffected. A fracture analysis of the tested UO₂ samples indicated a mixture of intergranular and transgranular fracture that transitions to transgranular fracture with increasing distance from the fracture origin. The characteristic strength of the combined data sets was determined to be 148 MPa, and the Weibull modulus was determined to be 9.1. The TRS values and Weibull parameters were close to values found in the literature for alternative testing techniques using samples with similar microstructure and density. The findings in this study validate the ball-on-ring method used to obtain the TRS of UO₂ with a sample geometry more representative of nuclear fuels. Additionally, experimental TRS results from this study can be implemented in modeling codes to predict fuel performance, which is critical to fuel burnup extension and advanced nuclear fuel technologies.

View Accepted Manuscript (DOE)

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE), Nuclear Fuel Cycle and Supply Chain. Advanced Fuel Campaign

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 2333856

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: 1 Vol. 589; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (54)

Fracture of Ceramics Danzer, R.; Lube, T.; Supancic, P. Advanced Engineering Materials, Vol. 10, Issue 4 https://doi.org/10.1002/adem.200700347	journal	April 2008
Ball‐on‐ring test validation for equibiaxial flexural strength testing of engineered ceramics Lupercio, Adrianna E.; Moshkelgosha, Ehsan; Winters, Riley C. International Journal of Ceramic Engineering & Science, Vol. 3, Issue 3 https://doi.org/10.1002/ces2.10085	journal	March 2021
Hertzian Fracture Fischer-Cripps, Anthony C. Introduction to Contact Mechanics https://doi.org/10.1007/978-0-387-68188-7_7	book	January 2007
The influence of grain size on the creep of uranium dioxide Burton, B.; Reynolds, G. L.; Barnes, J. P. Journal of Materials Science, Vol. 8, Issue 12 https://doi.org/10.1007/BF02403517	journal	December 1973
Weibull statistical fracture theory for the fracture of ceramics Petrovic, J. J. Metallurgical Transactions A, Vol. 18, Issue 11 https://doi.org/10.1007/BF02647012	journal	November 1987
Fracture Toughness of VVER and PWR Uranium-Dioxide Fuel Pellets with Different Grain Size Novikov, V. V.; Sivov, R. B.; Mikheev, E. N. Atomic Energy, Vol. 118, Issue 2 https://doi.org/10.1007/s10512-015-9965-x	journal	June 2015
Sintering Trajectories: Description on How Density, Surface Area, and Grain Size Change German, Randall M. JOM, Vol. 68, Issue 3 https://doi.org/10.1007/s11837-015-1795-8	journal	January 2016
Multi-Dimensional Simulation of LWR Fuel Behavior in the BISON Fuel Performance Code Williamson, R. L.; Capps, N. A.; Liu, W. JOM, Vol. 68, Issue 11 https://doi.org/10.1007/s11837-016-2115-7	journal	September 2016
Grain Boundary and Lattice Fracture Toughness of UO2 Measured Using Small-Scale Mechanics Feng, Lin; Finkeldei, Sarah C.; Heuser, Brent JOM, Vol. 72, Issue 5 https://doi.org/10.1007/s11837-020-04118-3	journal	March 2020
Observations and mechanisms of fracture in polycrystalline alumina Gutshall, Paul L.; Gross, Gordon E. Engineering Fracture Mechanics, Vol. 1, Issue 3 https://doi.org/10.1016/0013-7944(69)90005-8	journal	April 1969
Strength of ceramic materials containing small flaws Usami, S.; Kimoto, H.; Takahashi, I. Engineering Fracture Mechanics, Vol. 23, Issue 4 https://doi.org/10.1016/0013-7944(86)90120-7	journal	January 1986
The strength and fracture of stoichiometric polycrystalline UO2 Evans, A. G.; Davidge, R. W. Journal of Nuclear Materials, Vol. 33, Issue 3 https://doi.org/10.1016/0022-3115(69)90019-1	journal	December 1969
Effect of fabrication parameters and microstructure on the mechanical strength of UO2 fuel pellets Radford, K. C. Journal of Nuclear Materials, Vol. 84, Issue 1-2 https://doi.org/10.1016/0022-3115(79)90165-X	journal	October 1979
Resinter testing in relation to in-pile densification Maier, G.; Assmann, H.; Dörr, W. Journal of Nuclear Materials, Vol. 153 https://doi.org/10.1016/0022-3115(88)90213-9	journal	April 1988
Mechanical behaviour modelling of fractured nuclear fuel pellets Bernaudat, C. Nuclear Engineering and Design, Vol. 156, Issue 3 https://doi.org/10.1016/0029-5493(94)00962-X	journal	June 1995
Influence of support friction on three-point bend test Doz, Graciela N.; Riera, Jorge D. International Journal of Pressure Vessels and Piping, Vol. 51, Issue 3 https://doi.org/10.1016/0308-0161(92)90108-R	journal	January 1992
A model for microcrack initiation and propagation beneath hertzian contacts in polycrystalline ceramics Lawn, B. R.; Padture, N. P.; Guiberteau, F. Acta Metallurgica et Materialia, Vol. 42, Issue 5 https://doi.org/10.1016/0956-7151(94)90378-6	journal	May 1994
Mechanical properties of (U,Ce)O2 Yamada, Kazuhiro; Yamanaka, Shinsuke; Katsura, Masahiro Journal of Alloys and Compounds, Vol. 271-273 https://doi.org/10.1016/S0925-8388(98)00190-X	journal	June 1998
A practical and systematic review of Weibull statistics for reporting strengths of dental materials Quinn, Janet B.; Quinn, George D. Dental Materials, Vol. 26, Issue 2 https://doi.org/10.1016/j.dental.2009.09.006	journal	February 2010
Experimental and numerical study of fracture mechanisms in UO2 nuclear fuel Gatt, J. -M.; Sercombe, J.; Aubrun, I. Engineering Failure Analysis, Vol. 47 https://doi.org/10.1016/j.engfailanal.2014.07.019	journal	January 2015
Effect of competing mechanisms on fracture toughness of metals with ductile grain structures Li, Yan; Zhou, Min Engineering Fracture Mechanics, Vol. 205 https://doi.org/10.1016/j.engfracmech.2018.11.006	journal	January 2019
Ceramic nuclear fuel fracture modeling with the extended finite element method Jiang, Wen; Spencer, Benjamin W.; Dolbow, John E. Engineering Fracture Mechanics, Vol. 223 https://doi.org/10.1016/j.engfracmech.2019.106713	journal	January 2020
Molecular dynamics simulations of intergranular fracture in UO2 with nine empirical interatomic potentials Zhang, Yongfeng; Millett, Paul C.; Tonks, Michael R. Journal of Nuclear Materials, Vol. 452, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.05.034	journal	September 2014
Experimental characterization and modeling of UO 2 grain boundary cracking at high temperatures and high strain rates Salvo, Maxime; Sercombe, Jérôme; Helfer, Thomas Journal of Nuclear Materials, Vol. 460 https://doi.org/10.1016/j.jnucmat.2015.02.018	journal	May 2015
Unit mechanisms of fission gas release: Current understanding and future needs Tonks, Michael; Andersson, David; Devanathan, Ram Journal of Nuclear Materials, Vol. 504 https://doi.org/10.1016/j.jnucmat.2018.03.016	journal	June 2018
Nano- and micro-indentation testing of sintered UO2 fuel pellets with controlled microstructure and stoichiometry Gong, Bowen; Frazer, David; Yao, Tiankai Journal of Nuclear Materials, Vol. 516 https://doi.org/10.1016/j.jnucmat.2019.01.021	journal	April 2019
Mechanistic grain growth model for fresh and irradiated UO2 nuclear fuel Tonks, Michael R.; Simon, Pierre-Clément A.; Hirschhorn, Jacob Journal of Nuclear Materials, Vol. 543 https://doi.org/10.1016/j.jnucmat.2020.152576	journal	January 2021
High-burnup fuel stress analysis prior to and during a LOCA transient Capps, Nathan; Sweet, Ryan; Harp, Jason Journal of Nuclear Materials, Vol. 556 https://doi.org/10.1016/j.jnucmat.2021.153194	journal	December 2021
Ceramic nuclear fuel performance and the role of atomic scale simulations Cooper, M. W. D. Journal of Nuclear Materials, Vol. 561 https://doi.org/10.1016/j.jnucmat.2022.153531	journal	April 2022
Experimentally validated multiphysics modeling of fracture induced by thermal shocks in sintered UO2 pellets McClenny, Levi D.; Butt, Moiz I.; Abdoelatef, M. Gomaa Journal of Nuclear Materials, Vol. 565 https://doi.org/10.1016/j.jnucmat.2022.153719	journal	July 2022
Dry in-pile fracture test (DRIFT) for separate-effects validation of ceramic fuel fracture models Spencer, Benjamin W.; Woolstenhulme, Nicolas E.; Schulthess, Jason L. Journal of Nuclear Materials, Vol. 568 https://doi.org/10.1016/j.jnucmat.2022.153816	journal	September 2022
Empirical and mechanistic transient fission gas release model for high-burnup LOCA conditions Capps, Nathan; Aagesen, Larry; Andersson, David Journal of Nuclear Materials, Vol. 584 https://doi.org/10.1016/j.jnucmat.2023.154557	journal	October 2023
Analysis on the mechanical strength of WC-Co cemented carbides under uniaxial and biaxial bending Torres, Y.; Bermejo, R.; Gotor, F. J. Materials & Design, Vol. 55 https://doi.org/10.1016/j.matdes.2013.10.051	journal	March 2014
Weibull statistics effective area and volume in the ball-on-ring testing method Frandsen, Henrik Lund Mechanics of Materials, Vol. 73 https://doi.org/10.1016/j.mechmat.2013.10.010	journal	June 2014
Development and demonstration of a methodology to evaluate high burnup fuel susceptibility to pulverization under a loss of coolant transient Capps, Nathan; Sweet, Ryan; Wirth, Brian D. Nuclear Engineering and Design, Vol. 366 https://doi.org/10.1016/j.nucengdes.2020.110744	journal	September 2020
Integral LOCA fragmentation test on high-burnup fuel Capps, Nathan; Yan, Yong; Raftery, Alicia Nuclear Engineering and Design, Vol. 367 https://doi.org/10.1016/j.nucengdes.2020.110811	journal	October 2020
The transverse flexure of thin elastic plates supported at several points Bassali, W. A. Mathematical Proceedings of the Cambridge Philosophical Society, Vol. 53, Issue 3 https://doi.org/10.1017/S0305004100032795	journal	July 1957
Oxidation of Uranium Dioxide (UO2) GeØNvold, Fredrik; Haraldsen, Haakon Nature, Vol. 162, Issue 4106 https://doi.org/10.1038/162069a0	journal	July 1948
Microstructure Effects on Fracture Strength of U0 ² Fuel Pellets Oguma, Masaomi Journal of Nuclear Science and Technology, Vol. 19, Issue 12 https://doi.org/10.1080/18811248.1982.9734249	journal	December 1982
The Phenomena of Rupture and Flow in Solids Griffith, A. A. Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences, Vol. 221, Issue 582-593 https://doi.org/10.1098/rsta.1921.0006	journal	January 1921
Effect of Particle Size on Bulk Density and Strength Properties of Uranium Dioxide Specimens Burdick, M. D.; Parker, H. S. Journal of the American Ceramic Society, Vol. 39, Issue 5 https://doi.org/10.1111/j.1151-2916.1956.tb15641.x	journal	May 1956
Flexural Strength of Specimens Prepared from Several Uranium Dioxide Powders; Its Dependence on Porosity and Grain Size and the Influence of Additions of Titania Knudsen, F. P.; Parker, H. S.; Burdick, M. D. Journal of the American Ceramic Society, Vol. 43, Issue 12 https://doi.org/10.1111/j.1151-2916.1960.tb13633.x	journal	December 1960
Mechanical Properties of Pure, Dense Aluminum Oxide as a Function of Temperature and Grain Size Spriggs, R. M.; Mitchell, J. B.; Vasilos, T. Journal of the American Ceramic Society, Vol. 47, Issue 7 https://doi.org/10.1111/j.1151-2916.1964.tb12994.x	journal	July 1964
Deformation of UO2 at High Temperatures Canon, R. F.; Roberts, J. T. A.; Beals, R. J. Journal of the American Ceramic Society, Vol. 54, Issue 2 https://doi.org/10.1111/j.1151-2916.1971.tb12230.x	journal	February 1971
Biaxial and Uniaxial Data for Statistical Comparisons of a Ceramic's Strength Giovan, M. N.; Sines, George Journal of the American Ceramic Society, Vol. 62, Issue 9-10 https://doi.org/10.1111/j.1151-2916.1979.tb19117.x	journal	September 1979
Effect of Grain Size and Poling on the Fracture Mode of Lead Zirconate Titanate Ceramics Kim, Sang-Beom; Kim, Doh-Yeon; Kim, Jeong-Joo Journal of the American Ceramic Society, Vol. 73, Issue 1 https://doi.org/10.1111/j.1151-2916.1990.tb05113.x	journal	January 1990
Indentation of Ceramics with Spheres: A Century after Hertz Lawn, Brian R. Journal of the American Ceramic Society, Vol. 81, Issue 8 https://doi.org/10.1111/j.1151-2916.1998.tb02580.x	journal	August 1998
Weibull Strength Scaling for Standardized Rectangular Flexure Specimens Quinn, George D. Journal of the American Ceramic Society, Vol. 86, Issue 3 https://doi.org/10.1111/j.1151-2916.2003.tb03329.x	journal	March 2003
Effect of Grain Size on Mechanical Properties of Submicrometer 3Y‐TZP: Fracture Strength and Hydrothermal Degradation Eichler, Jens; Rödel, Jürgen; Eisele, Ulrich Journal of the American Ceramic Society, Vol. 90, Issue 9 https://doi.org/10.1111/j.1551-2916.2007.01643.x	journal	July 2007
A Statistical Distribution Function of Wide Applicability Weibull, Waloddi Journal of Applied Mechanics, Vol. 18, Issue 3 https://doi.org/10.1115/1.4010337	journal	September 1951
Influence of Test Method on Failure Stress of Brittle Dental Materials Ban, S.; Anusavice, K. J. Journal of Dental Research, Vol. 69, Issue 12 https://doi.org/10.1177/00220345900690120201	journal	December 1990
Biaxial flexural strength of Turkom-Cera core compared to two other all-ceramic systems Al-Makramani, Bandar Mohammed Abdullah; Razak, Abdul Aziz Abdul; Abu-Hassan, Mohamed Ibrahim Journal of Applied Oral Science, Vol. 18, Issue 6 https://doi.org/10.1590/S1678-77572010000600012	journal	December 2010
A Comparison of the Mechanical Properties of Three Glass-Ionomer Cements Poolthong, Suchit; Mori, Toshiko; Swain, Michael V. Dental Materials Journal, Vol. 13, Issue 2 https://doi.org/10.4012/dmj.13.220	journal	January 1994
Machining Cracks in Finished Ceramics Quinn, George D.; Ives, Lewis K.; Jahanmir, S. Key Engineering Materials, Vol. 290 https://doi.org/10.4028/www.scientific.net/KEM.290.1	journal	July 2005

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