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Thermodynamic properties of uranium plutonium mixed carbides

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Abstract

High plutonium containing hyperstoichiometric mixed carbide fuels are used as driver fuel in the Fast Breeder Test Reactor at Kalpakkam, India. The enthalpy increment of the mixed carbide fuels were measured in the temperature range 1000–1800 K using a high temperature drop calorimeter. The results are presented and compared with the data available in the literature.

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Correspondence to K. Nagarajan.

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Kandan, R., Babu, R. & Nagarajan, K. Thermodynamic properties of uranium plutonium mixed carbides. J Therm Anal Calorim 99, 713–717 (2010). https://doi.org/10.1007/s10973-009-0189-y

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  • DOI: https://doi.org/10.1007/s10973-009-0189-y

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