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Molten-salt reactors for efficient nuclear fuel utilization without plutonium separation [electronic resource]

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Bibliographic Details
Online Access:	Online Access
Corporate Author:	Oak Ridge National Laboratory (Researcher)
Format:	Government Document Electronic eBook
Language:	English
Published:	Oak Ridge, Tenn. : Oak Ridge, Tenn. : Oak Ridge National Laboratory. ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1978.
Subjects:	Design. Heavy Nuclei. Nuclear Fuels. Separation Processes. Even-odd Nuclei. Actinide Isotopes. Isotopes. Molten Salt Reactors. Fuel Cycle. Molten Salt Fuels. Fuels. Uranium 233. Reprocessing. Uranium Isotopes. Energy Sources. Planning. Breeder Reactors. Reactor Materials. Reactors. Actinide Nuclei. Liquid Fuels. Alpha Decay Radioisotopes. Nuclei. Radioisotopes. Years Living Radioisotopes. Nuclear Fuel Cycle And Fuel Materials. Specific Nuclear Reactors And Associated Plants.

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Call Number:	E 1.99:ornl/tm-6413
E 1.99:ornl/tm-6413	Available