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首页> 外文期刊>Journal of thermal analysis and calorimetry >Thermodynamic properties of uranium plutonium mixed carbides
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Thermodynamic properties of uranium plutonium mixed carbides

机译:Thermodynamic properties of uranium plutonium mixed carbides

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摘要

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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