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Shepherd, JS; Fairweather, M; Heggs, PJ; Hanson, BC (2015)
Publisher: Elsevier
Languages: English
Types: Article
Uranium carbide is a candidate fuel for future nuclear reactors. However, for it to be implemented in a closed fuel cycle, an outline for its reprocessing is necessary. One proposed method is to oxidise the uranium carbide into uranium oxide which can then be reprocessed using current infrastructure. A mathematical model describing the heat and mass transfer processes involved in such an oxidation has been constructed. The available literature was consulted for reaction coefficients and information on reaction products. A stable and convergent numerical solution has been developed using a combination of finite-difference approximations of the differential equations. Completion times of approximately 3-30h are predicted given a spherical pellet with a radius of 9.35mm under varying initial conditions. The transient temperature distribution throughout the system is predicted, with a maximum temperature of 1458°C observed from an initial temperature of 500°C at an oxygen concentration of 3.15mol m‾³.
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    • Scott, C.D., Analysis of Combustion of Graphite-Uranium Fuels in a Fixed Bed or Moving Bed. Industrial & Engineering Chemistry Process Design and Development, 1966. 5(3): p. 223-233.
    • Naito, K., N. Kamegashira, T. Kondo, and S. Takeda, Isothermal Oxidation, of Uranium Monocarbide Powder under Controlled Oxygen Partial Pressures. Journal of Nuclear Science and Technology, 1976. 13(5): p. 260-267.
    • P. N. Rowe, K.T.K., J. B. Lewis, Heat and mass transfer from a single sphere in an extensive flowing fluid. Chemical Engineering Research and Design, 1965. 43a: p. 14- 31.
    • Vines, R.G., Measurement of the Thermal Conductivities of Gases at High Temperatures. Journal of Heat Transfer, 1960. 82(1): p. 48-52.
    • Howard, J.B., G.C. Williams, and D.H. Fine, Kinetics of carbon monoxide oxidation in postflame gases. Symposium (International) on Combustion, 1973. 14(1): p. 975-986.
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