Effect of homogenization and hot rolling on the mechanical properties, microstructure and corrosion behavior of U–10Mo monolithic fuel

Prabhakaran, Ramprashad; Gardner, Levi; Joshi, Vineet; Burkes, Douglas; Lavender, Curt

doi:10.1016/j.jnucmat.2019.151804

Title: Effect of homogenization and hot rolling on the mechanical properties, microstructure and corrosion behavior of U–10Mo monolithic fuel

Journal Article · 30 November 2019 · Journal of Nuclear Materials

DOI: https://doi.org/10.1016/j.jnucmat.2019.151804 · OSTI ID:1570090

Prabhakaran, Ramprashad; Gardner, Levi; Joshi, Vineet; Burkes, Douglas; Lavender, Curt

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Sponsoring Organization:: USDOE National Nuclear Security Administration (NNSA)

OSTI ID:: 1570090

Alternate ID(s):: OSTI ID: 1614991; OSTI ID: 22886488

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: C Vol. 527; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: Netherlands

Language:: English

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Hydrolysis of Uranium Carbides between 25 and 100°. I. Uranium Monocarbide Bradley, Mildred J.; Ferris, Leslie M. Inorganic Chemistry, Vol. 1, Issue 3 https://doi.org/10.1021/ic50003a047	journal	August 1962
Microstructural analysis and corrosion behaviour of D9 stainless steel – Zirconium metal waste form alloys Bairi, Lipika Rani; Ningshen, S.; Mudali, U. Kamachi Corrosion Science, Vol. 52, Issue 7 https://doi.org/10.1016/j.corsci.2010.03.018	journal	July 2010
Electrochemical and corrosion behavior of a 304 stainless-steel-based metal alloy wasteform in dilute aqueous environments Chen, Jian; Asmussen, R. Matthew; Zagidulin, Dmitrij Corrosion Science, Vol. 66 https://doi.org/10.1016/j.corsci.2012.09.012	journal	January 2013
Characterization of U-2 wt% Mo and U-10 wt% Mo alloy powders prepared by centrifugal atomization Kim, Ki Hwan; Lee, Don Bac; Kim, Chang Kyu Journal of Nuclear Materials, Vol. 245, Issue 2-3 https://doi.org/10.1016/S0022-3115(97)00011-1	journal	June 1997
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
Thermodynamic studies on uranium–molybdenum alloys Parida, S. C.; Dash, S.; Singh, Z. Journal of Physics and Chemistry of Solids, Vol. 62, Issue 3 https://doi.org/10.1016/S0022-3697(00)00219-5	journal	March 2001
The anodic behaviour of low molybdenum-uranium alloys at higher electrolyte temperatures Mance, A. Journal of Nuclear Materials, Vol. 31, Issue 3 https://doi.org/10.1016/0022-3115(69)90221-9	journal	July 1969
Thermomechanical process optimization of U-10wt% Mo – Part 2: The effect of homogenization on the mechanical properties and microstructure Joshi, Vineet V.; Nyberg, Eric A.; Lavender, Curt A. Journal of Nuclear Materials, Vol. 465 https://doi.org/10.1016/j.jnucmat.2015.07.005	journal	October 2015
The effect of Anodamine on the corrosion behavior of 1018 mild steel in deionized water:I. Immersion and polarization tests Kuang, Wenjun; Mathews, James A.; Macdonald, Digby D. Electrochimica Acta, Vol. 127 https://doi.org/10.1016/j.electacta.2014.02.011	journal	May 2014
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
U-Mo Monolithic Fuel for Nuclear Research and Test Reactors Prabhakaran, Ramprashad JOM, Vol. 69, Issue 12 https://doi.org/10.1007/s11837-017-2612-3	journal	November 2017
Thermomechanical process optimization of U-10 wt% Mo – Part 1: high-temperature compressive properties and microstructure Joshi, Vineet V.; Nyberg, Eric A.; Lavender, Curt A. Journal of Nuclear Materials, Vol. 465 https://doi.org/10.1016/j.jnucmat.2013.10.065	journal	October 2015
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
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
Modeling the homogenization kinetics of as-cast U-10wt% Mo alloys Xu, Zhijie; Joshi, Vineet; Hu, Shenyang Journal of Nuclear Materials, Vol. 471 https://doi.org/10.1016/j.jnucmat.2015.11.026	journal	April 2016
Low-temperature irradiation behavior of uranium–molybdenum alloy dispersion fuel Meyer, M. K.; Hofman, G. L.; Hayes, S. L. Journal of Nuclear Materials, Vol. 304, Issue 2-3 https://doi.org/10.1016/S0022-3115(02)00850-4	journal	August 2002

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