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ZIRCEX AND MODIFIED ZIRFLEX PROCESSES FOR DISSOLUTION OF 8% U-91% Zr-1% H TRIGA REACTOR FUEL [electronic resource]

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Bibliographic Details
Online Access:	Online Access (via OSTI)
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. Department of Energy, 1961.
Subjects:	Additives. Aluminum. Aluminum Nitrates. Ammonium Compounds. Burnup. Combustion. Corrosion. Decontamination. Fluorides. Fluorination. Fuel Cans. Fuel Elements. Graphite. Graphite Moderator. Hydrides. Hydrochloric Acid. Hydrogen Peroxides. Laboratory Equipment. Mixing. Nitrates. Nitric Acid. Reprocessing. Separation Processes. Solutions. Solvent Extraction. Stainless Steels. Sulfuric Acid. Triga Series. Uranium Alloys. Uranium Chlorides. Uranium Hexafluoride. Volatility. Zircex Process. Zirconium Alloys. Zirconium Chlorides. Zirflex Process. Chemistry.

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Call Number:	E 1.99:ornl-3065
E 1.99:ornl-3065	Available