journal article·2019-02

Characterization of surface layers formed on DU10Mo ingots after processing steps and high humidity exposure

Tiffany C. Kaspar, Christina L. Arendt, Derek L. Neal, Shawn L. Riechers, Crystal Rutherford, Alan Schemer-Kohrn, Steven R. Spurgeon, Lucas E. Sweet, Vineet V. Joshi, Curt A. Lavender, Rick W. Shimskey

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Abstract

Abstract The design of monolithic U Mo fuel elements fabricated from low-enriched uranium for use in high-power research reactors requires bonding of the fuel foil to either Al cladding or a Zr barrier layer. Processing of the U Mo ingot to final foil form has the potential to generate surface layers on the foil that differ from the bulk, metallic U Mo. The interfacial properties between the U Mo and Zr or Al cladding layers will then be determined by these surface layers. We use x-ray photoelectron spectroscopy, cross-sectional scanning electron microscopy, and atomic force microscopy to characterize the composition, oxidation state, and morphology of the surface layers that form after hot rolling and cold rolling depleted U–10 wt% Mo alloy (DU10Mo). A thick uranium nitride layer is observed after hot rolling, although its origin is likely from a previous processing step. The efficacy of acid etching in HNO3 is compared to that of electropolishing in H2SO4 to remove surface nitride and oxide layers, and both methods are found to be similarly effective. Both laboratory (low humidity) air exposure and longer rinse times in water are shown to promote the formation of surface oxide layers. Exposure of both acid-etched and electropolished DU10Mo foils to humid air (97% relative humidity) for six weeks results in formation of a thick oxide layer due to corrosion. The oxide layer on the acid-etched foil is thicker and more highly oxidized than the oxide layer that forms on the electropolished foil, and these differences in oxidation behavior are attributed to higher surface roughness on the acid-etched foil. In general, Mo is found to play a role as a sacrificial element, typically exhibiting a larger ratio of Mo6+/Mo4+ than U6+/U4+. This is unexpected, given the greater thermodynamic driving force to form U oxides than Mo oxides.
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Research context

OpenAlex topics: Nuclear Materials and Properties · Radioactive element chemistry and processing · Nuclear reactor physics and engineering

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References (42)

Show source-provided references
1. High-density, low-enriched uranium fuel for nuclear research reactors10.1007/s11837-003-0031-0 ↗
2. Microstructural evolution of a uranium-10 wt.% molybdenum alloy for nuclear reactor fuels10.1016/j.jnucmat.2015.07.004 ↗
3. Review of 15 years of high-density low-enriched UMo dispersion fuel development for research reactors in Europe10.5516/NET.07.2014.703 ↗
4. Phase transformation of metastable cubic gamma-phase in U-Mo alloys10.1016/j.jallcom.2010.06.187 ↗
5. The kinetics of the isothermal decomposition of a gamma-phase uranium-6 atomic percent molybdenum alloy10.1016/0022-3115(63)90130-2 ↗
6. Development of characterisation methods on U(Mo) powders for material testing reactors (MTRs)10.1016/j.powtec.2013.10.048 ↗
7. Pore growth in U-Mo/Al dispersion fuel10.1016/j.jnucmat.2016.06.029 ↗
8. High burn-up structure of U(Mo) dispersion fuel10.1016/j.jnucmat.2016.04.035 ↗
9. Measurement of fission gas release from irradiated U-Mo dispersion fuel samples10.1016/j.jnucmat.2016.05.039 ↗
10. The influence of cladding on fission gas release from irradiated U-Mo monolithic fuel10.1016/j.jnucmat.2017.01.016 ↗
11. Microstructural anomalies in hot-isostatic pressed U-10 wt.% Mo fuel plates with Zr diffusion barrier10.1016/j.matchar.2015.03.015 ↗
12. Phase decomposition of gamma-U (bcc) in U-10 wt% Mo fuel alloy during hot isostatic pressing of monolithic fuel plate10.1016/j.jnucmat.2016.08.022 ↗
13. Microstructural characteristics of HIP-bonded monolithic nuclear fuels with a diffusion barrier10.1016/j.jnucmat.2014.02.004 ↗
14. Observed changes in as-fabricated U-10Mo monolithic fuel microstructures after irradiation in the advanced test reactor
15. Grain boundary engineering to control the discontinuous precipitation in multicomponent U10Mo alloy10.1016/j.actamat.2018.03.039 ↗
16. Effect of second phase particles and stringers on microstructures after rolling and recrystallization10.1016/j.msea.2018.08.040 ↗
17. A rate-theory-phase-field model of irradiation-induced recrystallization in UMo nuclear fuels
18. The effect of thermomechanical processing on second phase particle redistribution in U-10 wt%Mo10.1016/j.jnucmat.2017.12.042 ↗
19. Joshi · 2016
20. U-Zr alloy: XPS and TEM study of surface passivation10.1016/j.apsusc.2018.01.319 ↗
21. Dissolving uranium in nitric acid10.1021/ie50616a023 ↗
22. Dissolution of uranium metal and its alloys10.1021/ac50164a026 ↗
23. Nitric acid dissolution of uranium-molybdenum alloy reactor fuels10.1021/i260002a017 ↗
24. Hartree-slater subshell photoionization cross-sections at 1254 and 1487 eV10.1016/0368-2048(76)80015-1 ↗
25. High temperature oxidation of molybdenum in water vapor environments10.1016/j.jnucmat.2013.10.043 ↗
26. Epitaxial growth and properties of MoOx(2 < x < 2.75) films10.1063/1.1868852 ↗
27. XPS study of as-prepared and reduced molybdenum oxides10.1016/0169-4332(95)00317-7 ↗
28. Analysis of Mo(3d) XPS spectra of supported Mo catalysts - an alternative approach10.1021/j100156a054 ↗
29. XPS determination of uranium oxidation states10.1002/sia.3836 ↗
30. Quantifying small changes in uranium oxidation states using XPS of a shallow core level10.1039/C7CP05805E ↗
31. The passivation of uranium metal-surfaces by nitrogen bombardment - the formation of uranium nitride10.1016/0022-3115(88)90326-1 ↗
32. Preparation and photoelectron spectroscopy study of UNx thin films10.1016/S0925-8388(00)01307-4 ↗
33. The characterization of passive films on chromium electrodes by XPS10.1016/0010-938X(94)90014-0 ↗
34. Moulder · 1992
35. Mutual oxidation-states of uranium and molybdenum in U-Mo-O ternary oxides10.1016/0022-5088(90)90092-X ↗
36. Oxidation behavior of U-10 wt% Mo alloy in air at 473-773 K10.1016/S0022-3115(02)00905-4 ↗
37. Oxidation behavior of stainless steels 304 and 316 under the Venus atmospheric surface conditions10.1016/j.corsci.2018.01.002 ↗
38. Update on the chemical thermodynamics of uranium, neptunium, plutonium, americium and technetium
39. The enthalpies of formation of uranium mononitride and α-uranium and β-uranium sesquinitride by fluorine bomb calorimetry10.1016/0021-9614(81)90127-0 ↗
40. Calculation of enthalpies of formation of actinide nitrides10.1016/j.jnucmat.2005.04.013 ↗
41. Thermodynamic evidence for phase transition in MoO2-d10.1016/j.jct.2007.09.005 ↗
42. Lide · 2003