Analytical program for processing stainless steel uranium dioxide reactor fuel elements
George A. Huff, U.S. Atomic Energy Commission. Idaho Operations Office, Phillips Petroleum Company. Atomic Energy Division
Idaho Operations Office, U.S. Atomic Energy Commission, 1959 - Science - 24 pages
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Acid-Base Titration amounts of fission Amperometric Anal ANALYTICAL PROGRAM Atomic Energy Commission beaker Booman Chem Chemical Processing Plant Coarse Feed Constituent Determined contain large amounts conventional laboratory Cycle Extraction Column determining uranium Dilution Mass Spectrometer DIOXIDE REACTOR FUEL dissolution the uranium dissolve the stainless dissolver solution Duffy Extraction Column Feed Extraction Column Product Falling Drop Specific feed material fission products Huff ice bath Idaho Chemical Processing important Routine Samples infrared lamps Isotope Dilution Mass lead nitrate liquid-liquid solvent extraction Mass Spectrometer nitrate content nitric acid organic as possible Oxalate possible is poured procedure PROCESSING STAINLESS STEEL PROGRAM FOR PROCESSING reactor fuel elements Rein Remote Analytical Facility Remote Sulfate Titrator sample containing sample is added Samples of dissolver Shank slurry sodium hydroxide Specific Gravity Spectrophotometric STEEL URANIUM DIOXIDE stopper test tube thymol blue Tingey tube is added tube is transferred U. S. Atomic Energy U(VI uranium concentration URANIUM DIOXIDE REACTOR watch glass