Abstract
The isothermal oxidation behaviour of metallic uranium (U) and U–10wt.% molybdenum (U–10Mo) were studied by X-ray diffraction (XRD) and Thermogravimetric (TG) techniques in the temperature ranges of 473–673 K and 773–873 K, respectively. Dynamic (non-isothermal) TG plot was used to estimate the onset of breakaway oxidation and select the temperature regime for isothermal studies. Isothermal oxidation was used to study the kinetics of the oxidation reaction. It was found from XRD study that uranium was completely oxidised to U3O8 at 673 K after 3 h whereas in U–10Mo even at 848 K, α-U & UO2+x phases were present along with U3O8 at the end of 3 h. The activation energy for oxidation of U–10 wt% Mo was determined to be 120 kJ/mol in the temperature range of 773–873 K and that of uranium was 90 kJ/mol in the temperature range of 523–673 K. The oxidation resistance of U–10Mo could be attributed to both (i) isotropic γ-phase (bcc) of U-10Mo resulting in stable oxide film compared to that formed on α-phase (orthorhombic) uranium and (ii) lattice strain due to substitution of Mo in the oxide lattice which in turn retards the diffusion of oxygen through the oxide film.
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References
Snelgrove JL, Hofman G, Meyer M, Trybus C, Wiencek T (1997) Development of very-high-density low-enriched-uranium fuels. Nucl Eng Des 178:119–126
Meyer M, Clark C, Hayes S, Strain R, Hofman G, Snelgrove J, Park J, Kim K (1999) Irradiation behavior of Uranium-Molybdenum dispersion fuel: fuel performance data from RERTR-1 and RERTR-2
Sinha V, Hegde P, Prasad G, Dey G, Kamath H (2010) Phase transformation of metastable cubic γ-phase in U-Mo alloys. J Alloys Compd 506:253–262
Ajantiwalay T, Smith C, Keiser DD, Aitkaliyeva A (2020) A critical review of the microstructure of U-Mo fuels. J Nuclear Mater 152386
Baker L Jr, Bingle J (1966) The kinetics of oxidation of uranium between 300 and 625° C. J Nucl Mater 20:11–21
Loriers J (1959) Oxidation of metallic uranium. AEC Research and Development Report HW-61493
Ritchie A (1981) A review of the rates of reaction of uranium with oxygen and water vapour at temperatures up to 300 C. J Nucl Mater 102:170–182
Leibowitz L, Schnizlein J, Bingle J, Vogel R (1961) The kinetics of oxidation of uranium between 125 and 250 C. J Electrochem Soc 108:1155–1160
Barnartt S, Charles RG, Gulbransen EA (1957) Oxidation of 50 weight per cent uranium-zirconium alloy. J Electrochem Soc 104:218
Jain A, Sharma B, Manivannan A (2019) Oxidation behavior of U-6 mass% Zr alloy. J Therm Anal Calorim 136:1285–1293
Kang KH, Kim SH, Kwak KK, Kim CK (2002) Oxidation behavior of U–10 wt% Mo alloy in air at 473–773 K. J Nucl Mater 304:242–245
Matsui T, Yamada T, Ikai Y, Naito K (1993) Oxidation of U-20 at% Zr alloy in air at 423–1063 K. J Nucl Mater 199:143–148
Rao GR, Venugopal V, Sood D (1994) Oxidation studies on U–Zr alloys. J Nucl Mater 209:161–168
Roy S, Gupta N, Jat RA, Parida S, Mukerjee S (2016) Oxidation kinetics of UZr 2.3 and U 2 Ti alloys in dry air. Oxid Met 86:165–177
Greenholt CJ, Weirick LJ (1987) The oxidation of uranium-0.75 wt% titanium in environments containing oxygen and/or water vapor at 140° C. J Nucl Mater 144:110–120
Wood ES, White JT, Nelson AT (2017) Oxidation behavior of U-Si compounds in air from 25 to 1000 C. J Nucl Mater 484:245–257
McEachern RJ, Taylor P (1998) A review of the oxidation of uranium dioxide at temperatures below 400 C. J Nucl Mater 254:87–121
Sinha V, Hegde P, Prasad G, Dey G, Kamath H (2010) Effect of molybdenum addition on metastability of cubic γ-uranium. J Alloys Compd 491:753–760
Chychko A, Teng L, Seetharaman S (2010) MoO3 evaporation studies from binary systems towards choice of Mo precursors in EAF. Steel Res Int 81:784–791
Birks N, Meier GH, Pettit FS (2006) Introduction to the high temperature oxidation of metals. Cambridge University Press
Cathcart J (1973) Gaseous oxidation of uranium alloys. Oak Ridge National Lab, Tenn
Murch G, Catlow CRA (1987) Oxygen diffusion in UO 2, ThO 2 and PuO 2. A review. J Chem Soc Faraday Trans 2 Mol Chem Phys 83:1157–1169
Marin J, Contamin P (1969) Uranium and oxygen self-diffusion in UO2. J Nucl Mater 30:16–25
Matzke H (1969) On uranium self-diffusion in UO2 and UO2+x. J Nucl Mater 30:26–35
Belle J (1969) Oxygen and uranium diffusion in uranium dioxide (a review). J Nucl Mater 30:3–15
Acknowledgements
The authors thank Mr. Vivek Bhasin, Director, NFG & Mr. R.Keswani, Head, MFD for their constant support and encouragement during the course of this work. The authors also thank Dr. S.C. Parida, Head, PDD for providing the necessary support and guidance on working with Thermogravimetry and fruitful discussion during this work.
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R. Rakesh: Conceptualization, Synthesis, Characterization, Data analysis, Writing-original draft, S. P. Roy: Characterization, Writing-review & editing, Arihant Jain: Characterization, Data analysis, V. P. Sinha: Writing—review & editing, R. Tewari: Conceptualization, Writing—review & editing.
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Rakesh, R., Roy, S.P., Jain, A. et al. Oxidation behaviour of uranium and U–10wt.%Mo alloy in air. J Radioanal Nucl Chem 332, 3181–3190 (2023). https://doi.org/10.1007/s10967-023-08974-6
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DOI: https://doi.org/10.1007/s10967-023-08974-6