Mechanical properties examined by nanoindentation for selected phases relevant to the development of monolithic uranium-molybdenum metallic fuels

Newell, Ryan; Park, Youngjoo; Mehta, Abhishek; Keiser, Dennis; Sohn, Yongho

doi:10.1016/j.jnucmat.2017.02.018

Title: Mechanical properties examined by nanoindentation for selected phases relevant to the development of monolithic uranium-molybdenum metallic fuels

Journal Article · Thu Feb 16 00:00:00 EST 2017 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2017.02.018· OSTI ID:1405302

^[1]; Park, Youngjoo ^[1]; Mehta, Abhishek ^[1]; Keiser, Dennis ^[2]; Sohn, Yongho ^[1]

Univ. of Central Florida, Orlando, FL (United States). Dept. of Materials Science and Engineering
Idaho National Lab. (INL), Idaho Falls, ID (United States). Nuclear Fuels and Materials Division

Nanomechanical properties, specifically the reduced modulus and hardness of several intermetallic and solid solution phases are reported here to assist the development of the U-10 wt% Mo (U-10Mo) monolithic fuel system for research and test reactors. Findings from this study and reported values of mechanical properties provide data critical for understanding and predicting the structural behavior of the fuel system during fabrication and irradiation. The phases examined are products of interdiffusion and reaction between (1) the AA6061 cladding and the Zr diffusion barrier, namely (Al,Si)₃Zr and Al₃Zr, (2) the U-10Mo fuel and the Zr diffusion barrier, namely UZr₂, Mo₂Zr, and a-U, and (3) the U (or U-10Mo) and Mo, namely a mixture gradient of α- and γ-phases. The UC inclusions observed within the fuel alloy were also examined. Only phases present in thick or continuous microstructure on cross-sectioned fuel plates and diffusion couples were investigated for reduced modulus and hardness. Concentration-dependence of room-temperature reduced modulus in U solid solution with 0–10 wt% Mo was semi-quantitatively modeled based on mixture of α- and γ-phases and solid solutioning within the γ-phase.

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Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 1405302

Alternate ID(s):: OSTI ID: 1396890

Report Number(s):: INL/JOU-17-41448; PII: S0022311516306092

Journal Information:: Journal of Nuclear Materials, Vol. 487, Issue C; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 22 works

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References (39)

Development of very-high-density low-enriched-uranium fuels Snelgrove, J. L.; Hofman, G. L.; Meyer, M. K. Nuclear Engineering and Design, Vol. 178, Issue 1 https://doi.org/10.1016/S0029-5493(97)00217-3	journal	December 1997
Swelling of uranium by mechanical cavitation Angerman, C. L.; Caskey, G. R. Journal of Nuclear Materials, Vol. 13, Issue 2 https://doi.org/10.1016/0022-3115(64)90039-X	journal	January 1964
Fission product induced swelling of U–Mo alloy fuel Kim, Yeon Soo; Hofman, G. L. Journal of Nuclear Materials, Vol. 419, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.08.018	journal	December 2011
IRRADIATION PERFORMANCE OF U-Mo MONOLITHIC FUEL Meyer, M. K.; Gan, J.; Jue, J. F. Nuclear Engineering and Technology, Vol. 46, Issue 2 https://doi.org/10.5516/NET.07.2014.706	journal	April 2014
Microstructural analysis of as-processed U–10wt.%Mo monolithic fuel plate in AA6061 matrix with Zr diffusion barrier Perez, E.; Yao, B.; Keiser, D. D. Journal of Nuclear Materials, Vol. 402, Issue 1 https://doi.org/10.1016/j.jnucmat.2010.04.016	journal	July 2010
Microstructural characteristics of HIP-bonded monolithic nuclear fuels with a diffusion barrier Jue, Jan-Fong; Keiser, Dennis D.; Breckenridge, Cynthia R. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.02.004	journal	May 2014
Interdiffusion Between Zr Diffusion Barrier and U-Mo Alloy Huang, K.; Park, Y.; Keiser, D. D. Journal of Phase Equilibria and Diffusion, Vol. 33, Issue 6 https://doi.org/10.1007/s11669-012-0106-0	journal	September 2012
Growth kinetics and microstructural evolution during hot isostatic pressing of U-10wt.% Mo monolithic fuel plate in AA6061 cladding with Zr diffusion barrier Park, Y.; Yoo, J.; Huang, K. Journal of Nuclear Materials, Vol. 447, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.01.018	journal	April 2014
Diffusion Barrier Selection from Refractory Metals (Zr, Mo and Nb) Via Interdiffusion Investigation for U-Mo RERTR Fuel Alloy Huang, K.; Kammerer, C. C.; Keiser, D. D. Journal of Phase Equilibria and Diffusion, Vol. 35, Issue 2 https://doi.org/10.1007/s11669-013-0270-x	journal	November 2013
Interdiffusion and reactions between U–Mo and Zr at 650 °C as a function of time Park, Y.; Keiser, D. D.; Sohn, Y. H. Journal of Nuclear Materials, Vol. 456 https://doi.org/10.1016/j.jnucmat.2014.09.040	journal	January 2015
Microstructural anomalies in hot-isostatic pressed U–10 wt.% Mo fuel plates with Zr diffusion barrier Park, Y.; Eriksson, N.; Keiser, D. D. Materials Characterization, Vol. 103 https://doi.org/10.1016/j.matchar.2015.03.015	journal	May 2015
An improved technique for determining hardness and elastic modulus using load and displacement sensing indentation experiments Oliver, W. C.; Pharr, G. M. Journal of Materials Research, Vol. 7, Issue 06, p. 1564-1583 https://doi.org/10.1557/JMR.1992.1564	journal	June 1992
Measurement of hardness and elastic modulus by instrumented indentation: Advances in understanding and refinements to methodology Oliver, W. C.; Pharr, G. M. Journal of Materials Research, Vol. 19, Issue 1 https://doi.org/10.1557/jmr.2004.19.1.3	journal	January 2004
Development of the hot isostatic press manufacturing process for monolithic nuclear fuel Crapps, Justin; Clarke, Kester; Katz, Joel Nuclear Engineering and Design, Vol. 254 https://doi.org/10.1016/j.nucengdes.2012.09.002	journal	January 2013
Interdiffusion, Intrinsic Diffusion, Atomic Mobility, and Vacancy Wind Effect in γ(bcc) Uranium-Molybdenum Alloy Huang, Ke; Keiser, Dennis D.; Sohn, Yongho Metallurgical and Materials Transactions A, Vol. 44, Issue 2 https://doi.org/10.1007/s11661-012-1425-9	journal	October 2012
Stability, elastic properties and electronic structures of L12-ZrAl3 and D022-ZrAl3 up to 40GPa Duan, Y. H.; Sun, Y.; Peng, M. J. Journal of Physics and Chemistry of Solids, Vol. 75, Issue 4 https://doi.org/10.1016/j.jpcs.2013.12.014	journal	April 2014
First-principles calculations of elastic and thermodynamic properties of the four main intermetallic phases in Al–Zn–Mg–Cu alloys Li, C. M.; Zeng, S. M.; Chen, Z. Q. Computational Materials Science, Vol. 93 https://doi.org/10.1016/j.commatsci.2014.06.031	journal	October 2014
Adiabatic Elastic Moduli of Single Crystal Alpha‐Uranium Fisher, E. S.; McSkimin, H. J. Journal of Applied Physics, Vol. 29, Issue 10 https://doi.org/10.1063/1.1722972	journal	October 1958
Monte Carlo simulation of effective elastic constants of polycrystalline thin films Mullen, R. Acta Materialia, Vol. 45, Issue 6 https://doi.org/10.1016/S1359-6454(96)00366-7	journal	June 1997
Mechanical properties of L12 type Al3X (X = Mg, Sc, Zr) from first-principles study Fu, Lin; Ke, Jiang-Ling; Zhang, Quan physica status solidi (b), Vol. 249, Issue 8 https://doi.org/10.1002/pssb.201248011	journal	April 2012
In-situ TEM investigation of microstructural evolution in magnetron sputtered Al–Zr and Al–Zr–Si coatings during heat treatment Gudla, Visweswara Chakravarthy; Rechendorff, Kristian; Balogh, Zoltan Imre Materials & Design, Vol. 89 https://doi.org/10.1016/j.matdes.2015.10.081	journal	January 2016
Ambient- and high-temperature mechanical properties of isochronally aged Al–0.06Sc, Al–0.06Zr and Al–0.06Sc–0.06Zr (at.%) alloys Knipling, Keith E.; Seidman, David N.; Dunand, David C. Acta Materialia, Vol. 59, Issue 3 https://doi.org/10.1016/j.actamat.2010.10.017	journal	February 2011
Mechanical behavior and microcracking of cubic ternary zirconium trialuminides Virk, I. S.; Varin, R. A. Metallurgical Transactions A, Vol. 23, Issue 2 https://doi.org/10.1007/BF02801179	journal	February 1992
The U-Zr (Uranium-Zirconium) system Sheldon, R. I.; Peterson, D. E. Bulletin of Alloy Phase Diagrams, Vol. 10, Issue 2 https://doi.org/10.1007/BF02881432	journal	April 1989
On the formation mechanism of UZr2 phase Basak, Chandra Bhanu; Prabhu, N.; Krishnan, Madangopal Intermetallics, Vol. 18, Issue 9 https://doi.org/10.1016/j.intermet.2010.05.006	journal	September 2010
The lattice stability and structure of delta -UZr ₂ at elevated temperatures Akabori, M.; Ogawa, T.; Itoh, A. Journal of Physics: Condensed Matter, Vol. 7, Issue 43 https://doi.org/10.1088/0953-8984/7/43/005	journal	October 1995
Thermodynamic assessment of the Mo-Zr system Zinkevich, M.; Mattern, N. Journal of Phase Equilibria, Vol. 23, Issue 2 https://doi.org/10.1361/1054971023604242	journal	March 2002
First principles calculations of the structure and elastic constants of α, β and γ uranium Beeler, Benjamin; Deo, Chaitanya; Baskes, Michael Journal of Nuclear Materials, Vol. 433, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.09.019	journal	February 2013
Measuring the elastic properties of anisotropic materials by means of indentation experiments Vlassak, Joost J.; Nix, W. D. Journal of the Mechanics and Physics of Solids, Vol. 42, Issue 8 https://doi.org/10.1016/0022-5096(94)90033-7	journal	August 1994
On the determination of residual stress and mechanical properties by indentation Chen, Xi; Yan, Jin; Karlsson, Anette M. Materials Science and Engineering: A, Vol. 416, Issue 1-2 https://doi.org/10.1016/j.msea.2005.10.034	journal	January 2006
Properties of DU–10wt% Mo alloys subjected to various post-rolling heat treatments Burkes, Douglas E.; Prabhakaran, Ramprashad; Hartmann, Thomas Nuclear Engineering and Design, Vol. 240, Issue 6 https://doi.org/10.1016/j.nucengdes.2010.02.008	journal	June 2010
Microstructural characteristics of DU–xMo alloys with x=7–12wt% Burkes, Douglas E.; Hartmann, Thomas; Prabhakaran, Ramprashad Journal of Alloys and Compounds, Vol. 479, Issue 1-2 https://doi.org/10.1016/j.jallcom.2008.12.063	journal	June 2009
Neutron diffraction study of U–10 wt% Mo alloy Seong, Baek-Seok; Lee, Chang-Hee; Lee, Jeong-Soo Journal of Nuclear Materials, Vol. 277, Issue 2-3 https://doi.org/10.1016/S0022-3115(99)00198-1	journal	February 2000
Structural features of martensite α-phases in alloys of uranium with transition metals Orlov, V. K.; Teplinskaya, V. M. Atomic Energy, Vol. 86, Issue 2 https://doi.org/10.1007/BF02673532	journal	February 1999
Decomposition of a metastable solid solution in uranium-molybdenum alloy Orlov, V. K.; Teplinskaya, V. M.; Chebotarev, N. T. Atomic Energy, Vol. 88, Issue 1 https://doi.org/10.1007/BF02673318	journal	January 2000
Metastable phases in the uranium molybdenum system and their origin Tangri, K.; Williams, G. I. Journal of Nuclear Materials, Vol. 4, Issue 2 https://doi.org/10.1016/0022-3115(61)90129-5	journal	July 1961
A study of the shear transformations from the gamma-phase in uranium-molybdenum alloys containing 6.0–12.5 at % molybdenum Howlett, B. W. Journal of Nuclear Materials, Vol. 35, Issue 3 https://doi.org/10.1016/0022-3115(70)90212-6	journal	June 1970
Effect of molybdenum addition on metastability of cubic γ-uranium Sinha, V. P.; Hegde, P. V.; Prasad, G. J. Journal of Alloys and Compounds, Vol. 491, Issue 1-2 https://doi.org/10.1016/j.jallcom.2009.11.060	journal	February 2010
Properties of Uranium Monocarbide Smith, C. A.; Rough, Frank Nuclear Science and Engineering, Vol. 6, Issue 5 https://doi.org/10.13182/NSE59-A25677	journal	November 1959

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