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Reactor fuel reprocessing -- Equipment and supplies

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• Reactor fuel reprocessing
• Equipment and supplies

• Development of general tank-flow relationships with application to pilot plant data for a flooded column dissolver (U.S. Atomic Energy Commission, Idaho Operations Office, 1959), by E. E. Erickson, U. S. Atomic Energy Commission. Idaho Operations Office, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Application of tube-flow dissolver theory to data from a 2-inch, continuous flooded dissolver (U.S. Atomic Energy Commission, Idaho Operations Office, 1959), by E. E. Erickson, U. S. Atomic Energy Commission. Idaho Operations Office, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• A bench-scale natural-recirculation dissolver (U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by E. E. Erickson, Idaho Chemical Processing Plant, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Study of the feasibility of aqueous recovery of spent fuels. Part 5, Instrumentation design data (United States Atomic Energy Commission, Technical Information Service Extension, 1954), by M. H. Winsnes, U.S. Atomic Energy Commission, Consumers Power Company (Mich.), and University of Michigan. Engineering Research Institute (page images at HathiTrust)
• Construction materials for various head-end processes for the aqueous reprocessing of spent fuel elements (Battelle Memorial Institute, 1959), by Frederick W. Fink, James D. Jackson, P. D. Miller, Charles L. Peterson, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Equipment for nuclear fuel reprocessing (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1957), by Thomas J. Colven, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Study of the feasibility of aqueous recovery of spent fuels. Part 4, Equipment design data (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1954., 1954), by R. J. Annesser, H. A. Ohlgren, J. G. Lewis, R. J. Henig, U.S. Atomic Energy Commission, Consumers Power Company (Mich.), and University of Michigan. Engineering Research Institute (page images at HathiTrust)

Items below (if any) are from related and broader terms.

• Chemical processing and equipment. (McGraw-Hill, 1955), by American Society of Mechanical Engineers (page images at HathiTrust)
• Proposals affecting use of plutonium as a reactor fuel hearings before the Subcommittee on Energy and the Environment of the Committee on Interior and Insular Affairs, House of Representatives, Ninety-fifth Congress, first session, on H.R. 5234 ... H.R. 2145 ... April 26, 28, and 29, 1977. (U.S. Govt. Print. Off., 1977), by United States. Congress. House. Committee on Interior and Insular Affairs. Subcommittee on Energy and the Environment (page images at HathiTrust)
• Light water reactor fuel reprocessing and recycling. (Energy Research and Development Administration :;, 1977), by United States. Energy Research and Development Administration (page images at HathiTrust)
• Manufacture of fuel and blanket elements (Argonne National Laboratory, 1958), by C. C. Stone, F. D. Mc Cuaig, R. A. Noland, D. E. Walker, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
• Fabrication of the fuel and blanket for the Argonne Fast Source Reactor (AFSR) (Argonne National Laboratory, 1963), by W. R. Burt, U.S. Atomic Energy Comission, and Argonne National Laboratory. Metallurgy Division (page images at HathiTrust)
• A study of techniques and the development of equipment for decanning EBR-II fuel elements (Argonne National Laboratory, 1960), by J.P. Simon, U.S. Atomic Energy Comission, and Argonne National Laboratory. Remote Control Engineering Division (page images at HathiTrust)
• Preparation of alloy for first core loading of Experimental Breeder Reactor II (Argonne National Laboratory, 1961), by Donald C. Hampson, U.S. Atomic Energy Commission, and Argonne National Laboratory. Chemical Engineering Division (page images at HathiTrust)
• Interbuilding fuel transfer coffin for the Experimental Breeder Reactor II reactor (Argonne National Laboratory, 1964), by G. J. Bernstein, R. F. Malecha, A. A. Chilenskas, U.S. Atomic Energy Commission, and Argonne National Laboratory. Chemical Engineering Division (page images at HathiTrust)
• The manufacture of supplemental depleted fuel rods for Fuel Cycle Facility startup (Argonne National Laboratory, 1963), by N. J. Jr Carson, A. B. Shuck, H. F. Jelinek, U.S. Atomic Energy Commission, and Argonne National Laboratory. Metallurgy Division (page images at HathiTrust)
• Chlorination of uranium and fission product oxides in molten halide media (Argonne National Laboratory, 6546), by J. P. LaPlante, R. K. Steunenberg, D. A. Wenz, U.S. Atomic Energy Commission, and Argonne National Laboratory. Chemical Engineering Division (page images at HathiTrust)
• Nitridation of crucible skulls from melt refining (Argonne National Laboratory, 1960), by T. R. Johnson, R. K. Steunenberg, G. F. Brunzie, U.S. Atomic Energy Commission, and Argonne National Laboratory. Chemical Engineering Division (page images at HathiTrust)
• Stemming the plutonium tide : limiting the accumulation of excess weapon-usable nuclear materials : hearing before the Subcommittee on International Security, International Organizations, and Human Rights of the Committee on Foreign Affairs, House of Representatives, One Hundred Third Congress, second session, March 23, 1994. (U.S. G.P.O. :, 1994), by International Organizations United States. Congress. House. Committee on Foreign Affairs. Subcommittee on International Security (page images at HathiTrust)
• Denitration of purex wastes with sugar (U.S. Atomic Energy Commission, 1963), by L. A. Bray, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Chemical Research Operation (page images at HathiTrust)
• Air lift recirculation through UO₂ beds (U.S. Atomic Energy Commission, 1960), by F. D. Fisher, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Hanford Laboratories Operation (page images at HathiTrust)
• Ion exchange separation and coulometric titration of plutonium in irradiated fuel element solutions (U.S. Atomic Energy Commission, 1960), by J. W. Handshun, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Chemical Processing Department (page images at HathiTrust)
• The Sulfex process : terminal development report (U.S. Atomic Energy Commission, 1960), by F. D. Fisher, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Chemical Research and Development Operation (page images at HathiTrust)
• Yankee band cutting (U.S. Atomic Energy Commission, 1960), by V. L. Hammond, V. P. Kelley, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Chemical Research and Development Operation (page images at HathiTrust)
• Shear development for the nonproduction fuels reprocessing program (U.S. Atomic Energy Commission, 1961), by V. P. Kelley, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Chemical Research and Development Operation (page images at HathiTrust)
• Continuous dissolution of plutonium-bearing slag and crucible residues (Hanford Atomic Products Operation, 1961), by H. W. Crocker, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust)
• Demonstration of an irradiated UO₂ fuel recycle : first recycle (U.S. Atomic Energy Commission, 1961), by G. R. Horn, R. C. Smith, G. E. Benedict, J. L. Swanson, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust)
• Corrosion evaluation of nickel-base alloys developed to contain power reactor fuel dissolvents (U.S. Atomic Energy Commission, 1961), by R. F. Maness, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust)
• Vibrationally compacted ceramic fuels (Hanford Atomic Products Operation, 1961), by J. J. Hauth, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust)
• Reprocessing uranium-molybdenum alloy fuels : dissolution in concentrated nitric acid (U.S. Atomic Energy Commission, 1960), by W. W. Schulz, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Chemical Research and Development Operation (page images at HathiTrust)
• Darex pilot plant studies (U.S. Atomic Energy Commission, 1960), by J. J. Shefcik, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Chemical Research and Development Operation (page images at HathiTrust)
• Confinement and collection of UO₂ fines from a shearing operation (U.S. Atomic Energy Commission, 1960), by G. Rey, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust)
• Decontamination (U.S. Atomic Energy Commission, 1960), by P. S. Kingsley, M. L. Short, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust)
• Simulation of a recirculating, stirred chemical dissolver on an analog computer (U.S. Atomic Energy Commission, 1961), by Doc Taylor, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust)
• Low speed saw testing (U.S. Atomic Energy Commission, 1960), by V. L. Hammond, V. P. Kelley, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, Hanford Works, and Hanford Atomic Products Operation. Chemical Research and Development Operation (page images at HathiTrust)
• Shear development for the nonproduction fuel reprocessing program : interim report (U.S. Atomic Energy Commission, 1960), by V. P. Kelley, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Chemical Research and Development Operation (page images at HathiTrust)
• The preparation of uranium dioxide from a molten salt solution of uranyl chloride (U.S. Atomic Energy Commission, 1959), by W. L. Lyon, E. E. Voiland, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Chemical Research and Development Operation (page images at HathiTrust)
• Reprocessing of low-enrichment uranium-molybdenum alloy fuels (U.S. Atomic Energy Commission, 1959), by W. W. Schulz, E. M. Duke, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Chemical Research and Development Operation (page images at HathiTrust)
• The plutonium recycle program : a resum©Øe of the concept, program, and facilities (U.S. Atomic Energy Commission, 1957), by Hanford Atomic Products Operation, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, and Hanford Works (page images at HathiTrust)
• The effects of carbon content on the rate of dissolution of dingot uranium in nitric acid (U.S. Atomic Energy Commission, 1957), by A. L. Bement, J. L. Swanson, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust)
• Gamma radiolysis of tributyl phosphate-diluent systems (U.S. Atomic Energy Commission, 1957), by L. L. Burger, E. D. McClanahan, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Chemical Research and Development Operation (page images at HathiTrust)
• Power reactor fuels reprocessing progress report on corrosion studies (U.S. Atomic Energy Commission, 1959), by R. F. Maness, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Chemical Research and Development Operation (page images at HathiTrust)
• Concentration and final purification of neptunium by anion exchange (U.S. Atomic Energy Commission, 1959), by J. L. Ryan, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Chemical Research and Development Operation (page images at HathiTrust)
• Removal of chloride ion from Darex process dissolver solution (U.S. Atomic Energy Commission, 1959), by J. E. Mendel, W. W. Schulz, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Chemical Research and Development Operation (page images at HathiTrust)
• An analytical method for neptunium-237 using anion exchange (U.S. Atomic Energy Commission, 1959), by F. P. Roberts, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Chemical Research and Development Operation (page images at HathiTrust)
• The pilot plant denitration of purex wastes with formaldehyde (U.S. Atomic Energy Commission, 1959), by T. F. Evans, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Chemical Research and Development Operation (page images at HathiTrust)
• Tributyl phosphate-hydrocarbon diluent repurification in radiochemical processing at ORNL : status summary (Oak Ridge National Laboratory, 1960), by Wallace Davis, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Chemical Technology Division. Chemical Development Section B. (page images at HathiTrust)
• Corrosion associated with hydrofluorination in the Oak Ridge National Laboratory fluoride volatility process (Oak Ridge National Laboratory, 1961), by A. E. Goldman, A. P. Litman, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Metallurgy Division (page images at HathiTrust)
• Corrosion associated with fluorination in the Oak Ridge National Laboratory fluoride volatility process (Oak Ridge National Laboratory, 1961), by A. P. Litman, A. E. Goldman, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Metallurgy Division (page images at HathiTrust)
• Recovery of uranium and plutonium from sulfuric acid decladding solutions (Oak Ridge National Laboratory, 1959), by D. E. Horner, C. F. Coleman, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Chemical Technology Division. Chemical Development Section C. (page images at HathiTrust)
• Decladding of Consolidated Edison Power reactor fuel by Sulfex and Darex processes : cyclic dissolution experiments (Oak Ridge National Laboratory, 1960), by L. M. Ferris, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Chemical Technology Division. Chemical Development Section B. (page images at HathiTrust)
• Process for dissolution of Borax IV reactor fuel : laboratory development (Oak Ridge National Laboratory, 1960), by L. M. Ferris, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Chemical Technology Division. Chemical Development Section B. (page images at HathiTrust)
• Solvent extraction recovery of vanadium (and uranium) from acid liquors with di(2-ethylhexyl) phosphoric acid (Oak Ridge National Laboratory, 1959), by D. J. Crouse, K. B. Brown, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Chemical Technology Division. Chemical Development Section C. (page images at HathiTrust)
• Sulfex process : depassivation of stainless steel (Oak Ridge National Laboratory, 1959), by T. A. Gens, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Chemical Technology Division. Chemical Development Section B. (page images at HathiTrust)
• Design of chemical processing plant for homogenous reactor test (Oak Ridge National Laboratory, 1959), by A. M. Rom, H. O. Weeren, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Process Design Division (page images at HathiTrust)
• Progress report on the analysis of dissolver solutions by controlled-potential coulometric titration (Oak Ridge National Laboratory, 1959), by P. F. Thomason, E. L. Blevins, B. B. Hobbs, W. D. Shults, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Analytical Chemistry Division (page images at HathiTrust)
• Carburization and chemical treatments for recovery of uranium from stainless steel fuel elements (Oak Ridge National Laboratory, 1964), by R. E. Adams, E. S. Bomar, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Metals and Ceramics Division (page images at HathiTrust)
• Hydrofluoric acid decladding of zirconium-clad power reactor fuel elements (Oak Ridge National Laboratory, 1958), by W. E. Clark, A. H. Kibbey, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Chemical Technology Division. Chemical Development Section B. (page images at HathiTrust)
• Development of the Sulfex process for decladding stainless-steel-clad power reactor fuel elements with sulfuric acid (Oak Ridge National Laboratory, 1959), by A. H. Kibbey, J. H. Goode, W. E. Clark, J. R. Flanary, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Chemical Technology Division. Chemical Development Section B. (page images at HathiTrust)
• Thorex process : third uranium cycle studies (Oak Ridge National Laboratory, 1958), by J. R. Oliver, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Chemical Technology Division. Chemical Development Section A. (page images at HathiTrust)
• Dissolution of sintered thorium-uranium oxide fuel in nitric acid-fluoride solutions (Oak Ridge National Laboratory, 1958), by W. D. Bond, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Chemical Technology Division. Chemical Development Section B. (page images at HathiTrust)
• An analysis of power reactor fuel reprocessing (Oakridge National Laboratory, 1957), by C. D. Watson, H. E. Goeller, R. E. Blanco, F. L. Jr Culler, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory. Chemical Technology Division (page images at HathiTrust)
• Components of the fused-salt and sodium circuits of the aircraft reactor experiment (Oak Ridge National Laboratory, 1958), by W. B. McDonald, W. G. Cobb, G. D. Whitman, H. W. Savage, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory Reactor Projects Division (page images at HathiTrust)
• Fuel costs in spherical slurry reactors (Oak Ridge National Laboratory, 1957), by M. W. Rosenthal, T. B. Fowler, M. Tobias, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory Reactor Experimental Engineering Division (page images at HathiTrust)
• Removal of fission products from reactor wastes : Laboratory studies of liquid-liquid extraction from an acid aluminum nitrate solution (Oak Ridge National Laboratory, 1957), by Herman L. Krieger, Conrad P. Straub, B. Kahn, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory. Health Physics Division (page images at HathiTrust)
• Corrosion of stainless steel in acidic nitrate waste solutions from processing stainless steel reactor fuels (Oak Ridge National Laboratory, 1963), by W. E. Clark, E. S. Snavely, B. Willis, L. Rice, D. N. Hess, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Chemical Technology Division (page images at HathiTrust)
• Recovery of fission products from waste solutions by solvent extraction (Oak Ridge National Laboratory, 1963), by B. Weaver, K. B. Brown, D. J. Crouse, D. E. Horner, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Chemical Technology Division (page images at HathiTrust)
• Reduction of uranium hexafluoride retention on beds of magnesium fluoride used for removal of technetium hexafluoride (Oak Ridge National Laboratory, 1964), by Sidney Katz, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Chemical Technology Division. Chemical Development Section B. (page images at HathiTrust)
• Remote determination of fluoride in zirconium-uranium fuel processing solutions (Idaho Operations Office, U.S. Atomic Energy Commission, 1957), by James E. Rein, Maxine C. Elliott, Glenn L. Booman, Fred W. Dykes, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
• The effect of silicon in the reprocessing of a uranium aluminum alloy (Idaho Operations Office, U.S. Atomic Energy Commission, 1958), by K. L. Rohde, O. W. Parrett, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
• A gelatin-filtration headend for fuel reprocessing solutions from silicon-containing aluminum alloys (Idaho Operations Office, U.S. Atomic Energy Commission, 1959), by B. J. Newby, Bernice E. Paige, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
• Dissolution of zirconium alloys in lead chloride (Phillips Petroleum Company, Atomic Energy Division ; Idaho Operations Office, U.S. Atomic Energy Commission, 1959), by H. T. Hahn, E. M. Vander Wall, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
• Rapid two-cycle extraction method for neptunium : initial separation as neptunium (VI) with methyl isobutyl ketone (Idaho Operations Office, U.S. Atomic Energy Commission, 1959), by James E. Rein, M. C. Elliott, Glenn L. Booman, William J. Maeck, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
• Characterization of surfactants in aluminum-uranium fuel reprocessing solutions (Idaho Operations Office, U.S. Atomic Energy Commission, 1959), by R. D. Cannon, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
• Analytical program for processing stainless steel uranium dioxide reactor fuel elements (Idaho Operations Office, U.S. Atomic Energy Commission, 1959), by George A. Huff, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
• Dissolution of zirconium and zircaloy-2 in nitric-hydrofluoric acid mixtures at reflux temperatures (Idaho Operations Office, U.S. Atomic Energy Commission, 1960), by E. M. Vander Wall, D. L. Bauer, Elizabeth M. Whitener, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
• Barium fluozirconate precipitation from hydrofluoric acid : zirconium fuel reprocessing solutions. Part II, Fission product behavior (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by B. J. Newby, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Barium fluozirconate precipitation from hydrofluoric acid : zirconium fuel reprocessing solutions. Part I, Process chemistry (U.S. Atomic Energy Commission, Idaho Operations Office, 1960), by B. E. Paige, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Final report on decomposition of nitrous oxide (U.S. Atomic Energy Commission, Idaho Operations Office, 1960), by J. H. Zufall, H. S. Miller, Idaho National Reactor Testing Station, Air Reduction Company, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Modifications for the STR fuel recovery process (U.S. Atomic Energy Commission, Idaho Operations Office, 1960), by O. W. Parrett, Idaho Chemical Processing Plant. Chemical Development Branch, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Laboratory studies for Heat Transfer Reactor Experiment fuel reprocessing (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by R. D. Cannon, M. W. Roberts, K. L. Rohde, Bernice E. Paige, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• ARCO process definition and scoping studies (U.S. Atomic Energy Commission, Idaho Operations Office, 1960), by E. M. Vander Wall, D. L. Bauer, H. T. Hahn, Idaho National Reactor Testing Station, Idaho Chemical Processing Plant. Chemical Development Branch, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Electrostatic precipitation of submicron alumina particles (U.S. Atomic Energy Commission, Idaho Operations Office, 1960), by E. Hylsky, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Densities of ammonium fluoride-ammonium nitrate-ammonium hexafluozirconate solutions (U.S. Atomic Energy Commission, Idaho Operations Office, 1960), by J. L. Teague, D. P. Pearson, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Review of research and development at the Idaho Chemical Processing Plant on the electrolytic dissolution of nuclear fuel (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by C. M. Slansky, H. T. Hahn, K. L. Rohde, Idaho Chemical Processing Plant. Chemical Development Branch, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Interim report on the calcination of zirconium fluoride waste solutions (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by R. L. Hickok, J. S. Madachy, Idaho Chemical Processing Plant, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Pilot plant studies with a six-inch diameter fluidized bed calciner (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by D. R. Evans, E. S. Grimmett, Phillips Petroleum Company. Atomic Energy Division, Idaho National Reactor Testing Station, and Idaho Chemical Processing Plant (page images at HathiTrust)
• Physical and operational features of a pulsed continuous countercurrent liquid-solids contactor (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by E. S. Grimmett, B. P. Brown, Phillips Petroleum Company. Atomic Energy Division, Idaho National Reactor Testing Station, and Idaho Chemical Processing Plant (page images at HathiTrust)
• Cesium removal from acidic radioactive waste solutions (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by M. W. Wilding, Phillips Petroleum Company. Atomic Energy Division, Idaho National Reactor Testing Station, and Idaho Chemical Processing Plant (page images at HathiTrust)
• Plant tests on the decomposition of nitrous oxide over a heated rhodium catalyst (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by L. T. Lakey, Idaho Chemical Processing Plant, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Pneumatic atomizing nozzles in fluidized bed calcining. [Part] I, Calibration tests (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by Billy Mason Legler, J. I. Stevens, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Reprocessing uranium from the first Organic Moderated Reactor Experiment core (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by A. L. Ayers, G. J. Raab, Idaho Chemical Processing Plant, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Corrosion tests in molten lead-lead chloride (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by N. D. Stolica, M. R. Bomar, G. S. Adams, Phillips Petroleum Company. Atomic Energy Division, Idaho Chemical Processing Plant, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Remote dissolution and analytical program for irradiated thorium (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by George A. Huff, Idaho Chemical Processing Plant, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Interim report on the development of an air pulser for pulse column application (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by M. E. Weech, D. K. MacQueen, Robert Sterling P'Pool, Idaho Chemical Processing Plant, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Air lift performance at low liquid rates using oversized piping and lateral runs (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by H. V. Chamberlain, Idaho Chemical Processing Plant, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Mixing and evaporation in a packed vessel (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by G. K. Cederberg, J. A. Buckham, Idaho Chemical Processing Plant, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Series electrolytic dissolver for nuclear fuels. [Part] I, Scoping studies (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by M. R. Bomar, Idaho Chemical Processing Plant, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• The dissolution of iron and nickel in dilute aqua regia (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by Richard Douglas Cannon, Idaho Chemical Processing Plant, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Containment of iodine-131 released by the RaLa process (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by G. K. Cederberg, D. K. MacQueen, Idaho Chemical Processing Plant, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Laboratory studies of the rate of removal of stainless steel ions by mercury cathode electrolysis (U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by D. Richard Anderson, D. W. Rhodes, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Electrolytic oxidation of zirconium in nitrate solutions (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by M. R. Bomar, Idaho Chemical Processing Plant, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Electrolytic dissolution of nuclear fuels. Part II, Nichrome in nitrate solutions (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by J. R. Aylward, Elizabeth M. Whitener, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Electrolytic dissolution of nuclear fuels. Part I, Zirconium in HCl-methanol (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by J. R. Aylward, H. T. Hahn, Elizabeth M. Whitener, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Electrolytic dissolution of nuclear fuels. Part III, Stainless steel (304) in nitrate solutions (U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by J. R. Aylward, Elizabeth M. Whitener, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Catalyzed dissolution of uranium dioxide in lead chloride-chlorine systems (U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by E. M. Vander Wall, H. T. Hahn, D. L. Bauer, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Niobium behavior in the lead chloride and chlorine-lead chloride systems (U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by J. L. Teague, E. M. Vander Wall, H. T. Hahn, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Sodium fluozirconate precipitation process for zirconium fuels. Part I, Laboratory development (U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by B. J. Newby, Idaho Chemical Processing Plant, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Phase transformations in alumina (U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by H. J. Eding, A. G. Brown, M. L. Huggins, Stanford Research Institute, Idaho Chemical Processing Plant, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Development of a fluidized bed calcination process for aluminum nitrate wastes in a two-foot-square pilot plant calciner. Part I, Equipment development and initial process studies (U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by B. P. Brown, J. A. Buckham, E. S. Grimmett, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Development of a fluidized bed calcination process for aluminum nitrate wastes in a two-foot-square pilot plant calciner. Part II, Factors affecting the intra-particle porosity of alumina (U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by B. R. Wheeler, J. A. Buckham, E. S. Grimmett, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Thermal conductivity of alumina produced by the fluidized bed process (U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by Paul N. Kelly, Idaho Chemical Processing Plant, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• An improved aqueous process for zirconium alloy nuclear reactor fuels. Part I, Preliminary laboratory studies (U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by K. L. Rohde, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Thermal decomposition of hydrated iron, chromium, and nickel nitrates and their mixtures (U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by E. M. Vander Wall, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• The effect of radiation and nitric acid-nitrate salt solution on some non-metallic materials (U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by L. A. Decker, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Phase transformations in calcination of nitrates of aluminum, stainless steel, and nichrome (U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by H. J. Eding, A. G. Brown, M. L. Huggins, Stanford Research Institute, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Physical properties of nitrate solutions of iron- and nickel-base alloy nuclear fuels (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by D. P. Pearson, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• The in-line analysis of electrolytic dissolver solutions for nitric acid and salt concentrations (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by D. P. Pearson, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Evaluation of the metal-to-metal contact basket-type electrolytic dissolver (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by H. T. Hahn, M. R. Bomar, J. R. Aylward, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Effect of alloying constituents on aluminum dissolution rates (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by R. D. Fletcher, H. R. Beard, M. E. Jacobson, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Removal of particulates from waste calcining facility off-gas (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by R. D. Modrow, L. T. Lakey, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Development of fluidized bed calcination of aluminum nitrate wastes in the waste calcining facility (U.S. Atomic Energy Commission, Idaho Operations Office, 1965), by L. T. Lakey, W. P. Palica, G. E. Lohse, Idaho Chemical Processing Plant, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Testing of pumps for use in nitric acid-alumina slurry service (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by E. J. Bailey, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• A method of determining volumes and surface areas for groups of non-uniform sized particles (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by Earl S. Grimmett, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Development of a fluidized bed calcination process for aluminum nitrate wastes in a two-foot-square pilot plant calciner. Part III, Intermediate process studies--runs 11 through 22 (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by B. P. Brown, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• An improved aqueous process for zirconium alloy nuclear reactor fuels. Part II, Continuous dissolution with 5©œM hydrofluoric acid (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by B. J. Newby, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• A comparison of various calcination processes for processing high-level radioactive wastes (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by B. R. Wheeler, J. A. McBride, J. A. Buckham, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Determination of picric acid and mononitrophenols in ICPP process solutions (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by Stanley S. Yamamura, John H. Sikes, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Analog solution of a model of the sources of elutriatable fines in the fluidized bed calcination process (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by Earl S. Grimmett, Idaho National Reactor Testing Station, Phillips Petroleum Company. Atomic Energy Division, and Idaho Chemical Processing Plant (page images at HathiTrust)
• Development of a fluidized bed calcination process for aluminum nitrate wastes in a two-foot-square pilot plant calciner. Part IV, Final process studies--runs 23 through 37 (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by B. P. Brown, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Electrolytic dissolution of nuclear fuels with alternating current (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by F. M. Warzel, J. B. Colson, K. F. Smith, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Development of air distributor caps for a fluidized bed (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by J. C. Petrie, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Removal of tributyl phosphate and its degradation products from acidified uranyl nitrate solutions (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by H. T. Hahn, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Dry collection and disposition of solids from fluidized bed off-gas (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by J. C. Petrie, D. E. Black, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Pneumatic atomizing nozzles in fluidized bed calcining. [Part] II, Process tests (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by Billy Mason Legler, B. P. Brown, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Effect of recirculation of dissolver effluent on the continuous dissolution of aluminum in mercury-catalyzed nitric acid (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by R. H. Ray, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Reprocessing of coated OMRE fuel (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by L. A. Decker, M. E. Jacobson, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Solids flow control for a pulsed solids-liquid contactor (U.S. Atomic Energy Commission, Idaho Operations Office, 1965), by E. S. Grimmett, Noel De Nevers, Idaho Chemical Processing Plant, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Corrosion of type 316 stainless steel in NaK service : a literature survey (U.S. Atomic Energy Commission, Idaho Operations Office, 1965), by C. A. Zimmerman, Idaho Chemical Processing Plant, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Measurement of fission product leakage from fuel elements stored in water (U.S. Atomic Energy Commission, Idaho Operations Office, 1965), by D. W. Rhodes, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Decontamination of radioactive effluent with clinoptilolite (U.S. Atomic Energy Commission, Idaho Operations Office, 1965), by D. W. Rhodes, M. W. Wilding, Idaho Chemical Processing Plant, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• The design of a potentiostat for electrochemical research (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by R. H. Brown, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Progress report on volatility pilot plant corrosion problems to April 21, 1957 (Oak Ridge National Laboratory, 1958), by L. R. Trotter, E. E. Hoffman, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Metallurgy Division (page images at HathiTrust)
• Laboratory development of the thorex process : progress report, December 1, 1955 to January 1, 1958 (Oak Ridge National Laboratory, 1959), by R. H. Rainey, R. G. Mansfield, A. B. Meservey, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory (page images at HathiTrust)
• Chemical reprocessing plant. (U. S. Govt. Print. Off., 1964), by United States. Congress. Joint Committee on Atomic Energy (page images at HathiTrust; US access only)
• Construction management problems have delayed completion of the new plutonium facilities at Rocky Flats, Colorado : report (General Accounting Office, 1978), by United States General Accounting Office (page images at HathiTrust)
• Study of the feasibility of aqueous recovery of spent fuels. Part 5, Instrumentation design data (United States Atomic Energy Commission, Technical Information Service Extension, 1954), by M. H. Winsnes, U.S. Atomic Energy Commission, Consumers Power Company (Mich.), and University of Michigan. Engineering Research Institute (page images at HathiTrust)
• Study of the feasibility of aqueous recovery of spent fuels. Part 2, Properties of materials undergoing chemical processing (United States Atomic Energy Commission, Technical Information Service, 1954), by Joseph J. Bulmer, J. G. Lewis, H. A. Ohlgren, University of Michigan. Engineering Research Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Study of the feasibility of aqueous recovery of spent fuels. Part I, Dissolution experiments on alloy samples (United States Atomic Energy Commission, Technical Information Service, 1954), by Philip J. Elving, John O. Larson, John L. Griffin, and University of Michigan. Engineering Research Institute (page images at HathiTrust)
• Extraction of cesium polyiodides from synthetic waste solutions into nitrobenzene (Brookhaven National Laboratory, 1967), by Louis M. Slater, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Reprocessing of reactor fuels by volatization through the use of inert fluidized beds (Brookhaven National Laboratory, 1961), by J. J. Reilly, U.S. Atomic Energy Commission, Brookhaven National Laboratory, and Inc Associated Universities (page images at HathiTrust)
• Some methods of preparing tetravalent uranium solutions (Brookhaven National Laboratory, 1961), by H. Katz, U.S. Atomic Energy Commission, Brookhaven National Laboratory, and Inc Associated Universities (page images at HathiTrust)
• The recovery of fission product xenon and krypton by absorption processes (Brookhaven National Laboratory, 1959), by Meyer Steinberg, J. Pruzansky, Bernard Manowitz, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
• Catalytic decomposition of nitrous oxide (Brookhaven National Laboratory, 1959), by J. Pruzansky, Meyer Steinberg, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
• Waste processing development project : development of a waste calciner (Brookhaven National Laboratory, 1957), by Bernard Manowitz, V. Allen, S. Zwickler, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
• Studies on characteristics of Savannah River wastes : final report (Brookhaven National Laboratory, 1957), by Bernard Manowitz, V. Allen, C. W. Pierce, S. Zwickler, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
• An absorption process for recovery of fission product noble gases (Brookhaven National Laboratory, 1958), by M. Steinberg, Bernard Manowitz, Inc Associated Universities, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
• Disposal of solid wastes generated in fluidized-bed fluoride volatility fuel reprocessing (Brookhaven National Laboratory, 1968), by L. P. Hatch, C. Bartlett, R. Johnson, L. C. Emma, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Fluidized bed reprocessing of stainless steel clad UO₂ power reactor fuels (Brookhaven National Laboratory, 1965), by C. B. Bartlett, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Reprocessing of nuclear fuels by volatility separations in fluidized beds (Brookhaven National Laboratory, 1966), by S. J. Wachtel, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Reprocessing of power reactor fuels : the Enrico Fermi fast breeder reactor fuel progress report no. 1 (Brookhaven National Laboratory, 1958), by C. W. Pierce, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Reprocessing of power reactor fuels : the Enrico Fermi fast breeder reactor fuel progress report no. 2 (Brookhaven National Laboratory, 1959), by C. W. Pierce, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Monel and nickel corrosion in nonaqueous NO₂-HF solutions (Brookhaven National Laboratory, 1966), by Akiichi Kigoshi, Gerald Strickland, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Progress report on waste processing development project description of calciner pilot plant (Brookhaven National Laboratory, 1954), by F. Hittman, B. Manowitz, Inc Associated Universities, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
• Health Physics Division. (Oak Ridge National Laboratory, 1955), by Herman L. Krieger, Conrad P. Straub, B. Kahn, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory. Health Physics Division (page images at HathiTrust)
• Chemical Technology Division, Chemical Development Section B.. (Oak Ridge National Laboratory, 1961), by R. H. Rainey, J. G. Moore, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory. Chemical Technology Division (page images at HathiTrust)
• Bench-scale investigation of a process for aluminum-uranium alloy and stainless steel-cermet fuels (Argonne National Laboratory, Chemical Engineering Division, 1965), by D. Ramaswami, A. A. Jonke, Norman M. Levitz, U.S. Atomic Energy Commission, and Argonne National Laboratory. Chemical Engineering Division (page images at HathiTrust)
• Chemical Technology Dvision [and] Analytical Chemistry Division. (Oak Ridge National Laboratory, 1968), by J. W. Landry, G. A. West, W. J. Ross, J. E. Strain, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Evaluation of container materials for Zircex and Darex nuclear-fuel-recovery processes (Battelle Memorial Institute, 1957), by Frederick W. Fink, Earl L. White, Charles L. Peterson, P. D. Miller, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• The corrosion of type 347 stainless steel in boiling digest liquors (Battelle Memorial Institute ;, 1958), by Frederick W. Fink, Oliver M. Stewart, Walter J. Braun, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Description of a capsule for irradiation of fuel specimens at high temperatures (Battelle Memorial Institute ;, 1959), by Bruce W. Dunnington, William H. Goldthwaite, John H. Stang, S. J. Basham, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Construction materials for the hydrofluorinator of the fluoride-volatility process (Battelle Memorial Institute ;, 1959), by Frederick Fink, Elmer F. Stephan, Oliver M. Stewart, Charles L. Peterson, P. D. Miller, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Dissolution of irradiated consolidated Edison power-reactor fuel by the Sulfex and Darex processes (Battelle Memorial Institute ;, 1960), by R. A. Ewing, Duane Neuman Sunderman, Harvey B. Brugger, Battelle Memorial Institute, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory. Chemical Technology Division (page images at HathiTrust)
• Development of container materials for the fused chloride-electrolytic fuel-recovery process (Battelle Memorial Institute ;, 1961), by Walter K. Boyd, A. M. Hall, H. J. Wagner, Carl H. Lund, David C. Drennen, Earl L. White, Paul D. Miller, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Sulfex-thorex and darex-thorex dissolution of high-burnup consolidated edison reactor fuel (Battelle Memorial Institute ;, 1961), by R. A. Ewing, Duane Neuman Sunderman, Harvey B. Brugger, Battelle Memorial Institute, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory. Chemical Technology Division (page images at HathiTrust)
• Improved techniques for dispersing coated fuel particles in ceramic bodies (Battelle Memorial Institute ;, 1962), by Allison K. Smalley, Winston H. Duckworth, M. Clifford Brockway, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Separation of various components from uranium by oxidation-reduction reactions in a liquid KC1-LiC1/zinc system (Ames Laboratory, 1961), by P. Chiotti, Sidney J. S. Parry, U.S. Atomic Energy Commission, and Ames Laboratory (page images at HathiTrust)
• Equilibrium distribution data for purex and similar extraction processes (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1957), by Thomas H. Siddall, W. E. Prout, Sidney G. Parker, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• A miniature pilot plant for processing irradiated nuclear fuel (E.I. du Pont de Nemours & Company, Savannah River Laboratory, 1962), by William J. Jenkins, Edward C. Horni, Hugh E. Henry, Myron R. Caverly, Carl S. Schlea, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Uranium(IV) nitrate as a reducing agent for plutonium(IV) in the purex process (Du Pont de Nemours, Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1963), by William J. Jenkins, Hugh E. Henry, Myron R. Caverly, Carl S. Schlea, U.S. Atomic Energy Commission, E.I. du Pont de Nemours & Company, and Savannah River Laboratory (page images at HathiTrust)
• Purex process performance with short-residence contactors (Du Pont de Nemours, Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1963), by William J. Jenkins, Hugh E. Henry, Myron R. Caverly, Carl S. Schlea, U.S. Atomic Energy Commission, E.I. du Pont de Nemours & Company, and Savannah River Laboratory (page images at HathiTrust)
• Extraction behavior of zirconium at short residence times (E.I. du Pont de Nemours & Company, Savannah River Laboratory, 1963), by Albert A. Kishbaugh, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Recovery of uranium from zirconium-uranium alloy (E.I. du Pont de Nemours & Company, Savannah River Laboratory, 1963), by Hugh E. Henry, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Recovery of fission products from purex waste (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1964), by W. E. Prout, E. Kenneth Dukes, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Thermal fatigue tests : materials of construction for denitrator pots (E.I. du Pont de Nemours & Company, Savannah River Laboratory, 1964), by Louis P. Costas, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• A basin facility for examining irradiated nuclear fuel (E.I. du Pont de Nemours & Co., Savannah River Laboratory, 1964), by Frederick C. Locke, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Radiochemical seperations plant study : limited maintenance : Case VII (E.I. du Pont de Nemours & Co., Savannah River Laboratory, 1964), by Robert J. Christl, Clifford S. Otto, John E. Crawley, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Recovery of rare earth fission products from purex waste (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1960), by W. E. Prout, Ernest K. Dukes, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• In-line polarography of uranium in process waste (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1961), by Robert C. Propst, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Electrolytic dissolution of power reactor fuels in nitric acid (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1961), by A. Thomas Clark, U.S. Atomic Energy Commission, and Savannah River Laboratory (page images at HathiTrust)
• Solvent extraction data for plutonium : a compilation of data in the literature / by Linda Lou Smith. (E.I. du Pont de Nemours & Company, Savannah River Laboratory, 1962), by Linda Lou Smith, U.S. Atomic Energy Commission, Savannah River Laboratory, E.I. du Pont de Nemours & Company. Explosives Department, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Recovery of plutonium from irradiated plutonium-aluminum alloy (E.I. du Pont de Nemours & Company, Savannah River Laboratory, 1962), by William C. Perkins, Hugh E. Henry, William J. Jenkins, Myron R. Caverly, Carl S. Schlea, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Dissolver for natural uranium fuel elements (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1958), by Vincent P. Caracciolo, R. C. May, J. T. Grace, U.S. Atomic Energy Commission, and Savannah River Laboratory (page images at HathiTrust)
• Processing of fuel assemblies that contain zirconium (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1959), by Woodfin E. Shuler, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Neutron monitor for plutonium inventory control (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1958), by William A. Kropp, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Plutonium fuel fabrication and reprocessing for fast ceramic reactors (United States Atomic Energy Commission, Technical Information Service, 1962), by E. L. Zebroski, G.D. Collins, H.W. Alter, General Electric Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• A fuel reprocessing plant for fast ceramic reactors (U.S. Atomic Energy Commission, Division of Technical Information, 1962), by H. W. Alter, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Recovery of uranium from uranium-zirconium fuel scrap (U.S. Atomic Energy Commission, Union Carbide Nuclear Company, 1960), by T. P. Sprague, Oak Ridge Y-12 Plant, Union Carbide Nuclear Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• The behavior of representative fission products and plutonium in the KAPL electrorefining process and a review of the status of the process (Knolls Atomic Power Laboratory, General Electric Company, 1957), by L. W. Niedrach, G. R. Fountain, A. C. Glamm, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• Recovery of uranium from fused salt melts by electrodeposition (Knolls Atomic Power Laboratory, General Electric Company, 1957), by L. W. Niedrach, G. R. Fountain, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• Electrolytic recycle method for the treatment of radioactive nitric acid waste : a status report at the termination of the project at KAPL (Knolls Atomic Power Laboratory, General Electric Company, 1957), by H.W. Alter, F.J. Witt, A.C. Schafer, J.K. Davidson, Duane L. Barney, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• One-cycle process for the recovery and decontamination of plutonium (Knolls Atomic Power Laboratory, General Electric Company, 1957), by H. W. Alter, J. L. Mewherter, R. Fowler, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• Reprocessing uranium by the deBoer volatile iodide process (Knolls Atomic Power Laboratory, General Electric Company, 1957), by W. L. Robb, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• Evaluation of minor isotope safeguard techniques (MIST) in reactor fuel reprocessing (U.S. G.P.O., 1970), by U.S. Atomic Energy Commission and Inc Nuclear Fuel Services (page images at HathiTrust)
• Reprocessing of thorium-uranium fuels by liquid metal extraction (Atomics International, 1960), by R. E. Johnson, J. D. Chilton, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Pyroprocessing Refabrication Experiment quarterly progress report (Atomics International ;, in the 20th century), by U.S. Atomic Energy Commission. Technical Information Center and North American Aviation. Atomics International Division (page images at HathiTrust)
• Modified hot cave facility for reprocessing experiments (Atomics International, 1958), by S. Strausberg, T. H. Mills, T. E. Luebben, J. Guon, W. J. Gardner, U.S. Atomic Energy Commission, and North American Aviation. Atomics International Division (page images at HathiTrust)
• Low decontamination reprocessing studies on irradiated uranium oxide reactor fuel (Atomics International, 1962), by J. Guon, F. W. Gandolfo, R. J. Sullivan, J. E. Bodine, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Multicycle reprocessing and refabrication experiments on simulated UOb2s-fissia pellets (Atomics International, 1962), by S. Strausberg, T. E. Luebben, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• The oxide-drossing furnace for the Processing Refabrication Experiment (Atomics International, 1958), by J. L. Ballif, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Remote fabrication of Sodium Reactor Experiment fuel rods in the Processing Refabrication Experiment (Atomics International, 1959), by T. A. Golding, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Oxidation of uranium carbide by carbon dioxide (Atomics International, 1962), by E. W. Murbach, W. D. Turner, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Reprocessing studies on irradiated uranium carbide reactor fuel (Canoga Park, California : Atomics International, 1962., 1962), by J. E. Bodine, F. W. Gandolfo, R. J. Sullivan, J. Guon, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Reprocessing of uranium carbide by molten salt electrolysis (Canoga Park, Calif. : Atomics International, 1963., 1963), by W. N. Hansen, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• An elevating turntable for remote maintenance in the Processing-Refabrication Experiment (Atomics International, 1959), by Donald J. Stoker, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Decontamination of thorium-uranium alloys by consumable arc-melting (Atomics International, 1959), by R. E. Johnson, E. W. Murbach, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Removal of irradiated UOb2s fuel from the cladding by controlled oxidation (Atomics International, 1959), by L. A. Hanson, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Processing Refabrication Experiment (PRE) program bibliography (Atomics International, 1959), by G. L. Schalin, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Comparative fuel cycle evaluations low decontamination pyroprocessing vs. aqueous reprocessing . Part 1, UOb2s fuel in a thermal reactor (Canoga Park, California : Atomics International, 1963., 1963), by L. J. Colby, Walther Stoltzing, E. W. Murbach, H. Pearlman, K. L. Mattern, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Reprocessing of uranium-carbide by a nitrate-carbide cycle. [Part] I, Kinetics of nitride formation (Canoga Park, California : Atomics International, 1963., 1963), by L. A. Hanson, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Chemical pulverization of sintered uranium dioxide bodies. (Atomics International, 1959), by D. W. Reed, T. E. Luebben, S. Strausberg, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Preparation of uranium metal by carbon reduction (Canoga Park, California : Atomics International, 1963., 1963), by W. G. Smiley, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Kinetics of nitride conversion to carbide (Canoga Park, California : Atomics International, 1964., 1964), by L. A. Hanson, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
• Reprocessing of uranium carbide by a nitride--carbide cycle. III, Complete cycle and fission product study (Canoga Park, California : Atomics International, 1964., 1964), by L. A. Hanson, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
• Ultrasonic fuel reprocessing in mercury (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service, 1961., 1961), by W. B. Tarpley, C. Dana McKinney, U.S. Atomic Energy Commission. New York Operations Office, and Aeroprojects Incorporated (page images at HathiTrust)
• Pyrochemical reprocessing of uranium carbide : summary report (Atomics International, 1965), by E. W. Murbach, Walther Stoltzing, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Pyrochemical reprocessing of UOb2s by AIROX : summary report (Atomics International, 1965), by Walther Stoltzing, E. W. Murbach, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Decontamination of thorium-uranium alloy by nonconsumable electrode arc-melting (Atomics International, 1957), by E. W. Murbach, A. G. Buyers, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
• Gaseous chemical treatment of irradiated uranium dioxide (Atomics International, 1960), by J. Guon, F. D. Rosen, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Reprocessing of irradiated fission reactor fuel and breeding materials : an annotated bibliography of selected report literature (Oak Ridge, Tennessee : U.S. Atomic Energy Commission, Division of Technical Information, 1964., 1964), by James M. Jacobs and U.S. Atomic Energy Commission (page images at HathiTrust)
• Reprocessing of irradiated fission reactor fuel and breeding material : a literature search (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service, [1960], 1960), by James M. Jacobs and U.S. Atomic Energy Commission (page images at HathiTrust)
• Reprocessing of irradiated fission reactor fuel and breeding material : a literature search (Oak Ridge, Tennessee : United States Atomic Energy Commission, Division of Technical Information, [1961], 1961), by James M. Jacobs and U.S. Atomic Energy Commission (page images at HathiTrust)
• Handling and storage of conditioned high-level wastes (Vienna : International Atomic Energy Agency, 1983, 1983), by International Atomic Energy Agency (page images at HathiTrust)
• Report to the LMFBR Steering Committee on resources, fuel and fuel cycles, and proliferation aspects. (Energy Research and Development Administration, Office of the Assistant Administrator for Nuclear Energy ;, 1977), by United States. Energy Research and Development Administration. Office of the Assistant Administrator for Nuclear Energy (page images at HathiTrust)
• Raw materials conference on solvent extraction, held at Winchester, Massachusetts, January 17-18, 1955 (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1955., 1955), by Arthur M. Ross, National Lead Company. Raw Materials Development Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Symposium on the Reprocessing of Irradiated Fuels : held at Brussels, Belgium, May 20-25, 1957. Book 2. (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1957., 1957), by Symposium on the Reprocessing of Irradiated Fuels (1957 : Brussels) and U.S. Atomic Energy Commission (page images at HathiTrust)
• Fuel cycle costs for specific power reactors (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1961., 1961), by Donald W. Kuhn, R. D. Walton, and U.S. Atomic Energy Commission. Office of Operations Analysis and Forecasting (page images at HathiTrust)
• Contamination of zirconium-uranium by recycling of scrap (Pittsburgh, Pennsylvania : Bettis Plant, 1957., 1957), by L. F. Cochrun, J. C. Szurley, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Chemical processing of reactor fuel elements at the Idaho Chemical Processing Plant. Volume 6. Selected reference material, United States Atomic Energy Program (U.S. Government Printing Office, 1955), by U.S. Atomic Energy Commission (page images at HathiTrust)
• Quick and secret construction of plutonium reprocessing plants: a way to nuclear weapons proliferation? : report (U.S. General Accounting Office, 1980), by United States General Accounting Office (page images at HathiTrust)
• Radioactive waste processing and disposal. (Nuclear Regulatory Commission, 1980), by U.S. Nuclear Regulatory Commission. Office of Nuclear Material Safety and Safeguards. Division of Waste Management and Environmental Protection and United States. Department of Energy. Technical Information Center (page images at HathiTrust)
• Radioactive waste processing and disposal. ([Washington] : U.S. Nuclear Regulatory Commission ; Oak Ridge, TN : Department of Energy, 1980., 1980), by U.S. Nuclear Regulatory Commission. Office of Nuclear Material Safety and Safeguards. Division of Waste Management and Environmental Protection and United States. Department of Energy. Technical Information Center (page images at HathiTrust)
• Effect of plant size on costs of purex processing of heterogeneous power reactor fuel (Oak Ridge, Tennessee : U.S. Atomic Energy Commission, Technical Information Service, [date of publication not identified].), by J. W. Ullmann, United States. Department of Energy. Office of Scientific and Technical Information, and Oak Ridge National Laboratory (page images at HathiTrust)
• Survey of a site for a nuclear fuel processing plant and waste disposal area at Oak Ridge (U.S. Atomic Energy Commission, Technical Information Branch, 1967), by R. E. Blanco, F. L. Parker, T. F. Lomenick, R. E. Lampton, H. E. Goeller, K. E. Cowser, William John Boegly, J. O. Blomeke, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• The potential of using mixed fission products as a source of energy (Richland, Washington : Pacific Northwest Laboratory, 1969., 1969), by D. W. Bolme, Battelle Memorial Institute. Pacific Northwest Division, U.S. Atomic Energy Commission, and Pacific Northwest Laboratory (page images at HathiTrust)
• Unit operations section monthly progress report (Oak Ridge, Tennessee : U.S. Atomic Energy Commission, Technical Information Service, 1964., 1964), by M. E. Whatley, C. D. Watson, J. C. Suddath, A. D. Ryon, R. W. Horton, P. A. Haas, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory (page images at HathiTrust)
• Description of a pilot-scale facility for uranium dioxide-plutonium dioxide processing studies (Argonne National Laboratory, 1964), by G. J. Vogel, W. J. Mecham, E. L. Carls, and Argonne National Laboratory. Chemical Engineering Division (page images at HathiTrust)
• Zirconium processing capability of the Idaho Chemical Processing Plant (Idaho Operations Office, U.S. Atomic Energy Commission, 1964), by J. R. Bower, Phillips Petroleum Company. Atomic Energy Division, U.S. Atomic Energy Commission. Idaho Operations Office, and Idaho National Reactor Testing Station (page images at HathiTrust)
• A study of the feasibility of a small scale reprocessing plant for the Dresden Nuclear Power Station (Idaho Operations Office, U.S. Atomic Energy Commission, 1961), by H. Schneider, Phillips Petroleum Company. Atomic Energy Division, U.S. Atomic Energy Commission. Idaho Operations Office, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Conceptual study of a system for radioactive demonstration of the chop-leach process (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by J. A. Buckham, R. G. Pitkin, R. S. P'Pool, Vitro Engineering Company, Idaho National Reactor Testing Station, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
• Solvent extraction reprocessing method for irradiated uranium (Hanford Atomic Products Operation, 1957), by E. R. Irish, W. H. Reas, General Electric Company, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
• Pilot plant fluorination of uranium fuel elements by bromine trifluoride (Brookhaven National Laboratory, 1957), by G. Strickland, R. Johnson, F. L. Horn, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
• Chemical Technology Division (Oak Ridge National Laboratory, 1962), by F. G. Kitts, W. E. Clark, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• A process for the recovery of uranium from nuclear fuel elements using fluid-bed drying and volatility techniques (Argonne National Laboratory, Chemical Engineering Division, 1961), by N. Levitz and Argonne National Laboratory (page images at HathiTrust)
• Solidification of high-level radioactive fuel reprocessing wastes by spray and pot calcination : hot-cell pilot plant studies (Hanford Atomic Products Operation, 1964), by R. T. Allemann, U. L. Upson, F. P. Roberts, U.S. Atomic Energy Commission, Hanford Atomic Products Operation, Pacific Northwest Laboratory, and General Electric Company (page images at HathiTrust)
• Chemical reprocessing plant. Hearing before the Joint Committee on Atomic Energy, Congress of the United States, Eighty-eighth Congress, first session ... May 14, 1963. (U.S. Govt. Print. Off., 1964), by United States. Congress. Joint Committee on Atomic Energy (page images at HathiTrust)
• Description and proposed operation of the Fuel Cycle Facility for the second Experimental Breeder Reactor (EBR-II) (Argonne National Laboratory, Chemical Engineering Division, 1963), by J. C. Hesson, L. Burris, M. J. Feldman, and Argonne National Laboratory (page images at HathiTrust)
• Dissolution of power reactor fuel cores (Hanford Atomic Products Operation, 1960), by H. T. Blaine, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
• Application of the peripheral compressor to the fluoride volatility process (Oak Ridge, Tennessee : Oak Ridge Gaseous Diffusion Plant, Union Carbide Corporation Nuclear Division, 1969., 1969), by M. J. Stephenson, P. S. Cates, L. W. Anderson, Union Carbide Corporation. Nuclear Division, Oak Ridge Gaseous Diffusion Plant, and U.S. Atomic Energy Commission (page images at HathiTrust)
• AEC conceptual high-temperature gas-cooled reactor (HTGR) fuel processing plant ([Washington, D.C.] : United States Atomic Energy Commission, Division of Technical Information, 1970., 1970), by Idaho Nuclear Corporation, U.S. Atomic Energy Commission. Division of Technical Information, and U.S. Atomic Energy Commission. Division of Production (page images at HathiTrust)
• Model plutonium recycle reactors for environmental analysis of the mixed-oxide fuel cycle ([Washington, D.C.] : Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, 1978., 1978), by J. W. Wachter, Oak Ridge National Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Material Safety and Safeguards (page images at HathiTrust)
• Quarterly progress report on fission product behavior in LWRs for the Period October--December 1978 (Oak Ridge, Tennessee. : United States. Dept. of Energy. Office of Scientific and Technical Information, 1979., 1979), by A. P. Malinauskas, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, Oak Ridge National Laboratory, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• Nuclear reactor fuel reprocessing : selected references, 1976-1980 ([Washington, DC] : Library of Congress, Congressional Research Service, [1980], 1980), by B. F. Mangan and Library of Congress. Congressional Research Service (page images at HathiTrust)
• Benefit analysis of reprocessing and recycling light water reactor fuel. (U.S. Energy Research and Development Administration ;, 1976), by United States. Energy Research and Development Administration (page images at HathiTrust)
• Analytical methodology and facility description : spent fuel policy. (Washington, D. C. : Dept. of Energy, Assistant Secretary for Energy Technology, 1978., 1978), by United States. Department of Energy. Office of Energy Technology (page images at HathiTrust)
• Applications of ultrasonic energy to pyrometallurgical and pyrochemical processing of nuclear materials (West Chester, Pennsylvania : Aeroprojects Incorporated, 1961., 1961), by C. D. McKinney, R. S. Winchester, William Tarpley, U.S. Atomic Energy Commission. New York Operations Office, and Aeroprojects Incorporated (page images at HathiTrust)
• Rare gas recovery facility at the Idaho Chemical Processing Plant (Idaho Falls, Idaho : Idaho Nuclear Corporation, National Reactor Testing Station, 1969., 1969), by G. F. Offutt, C. L. Bendixsen, Idaho Operations Office U.S. Atomic Energy Commission, Allied Chemical Corporation, Aerojet-General Corporation, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Chemical Technology Division annual progress report for period ending ... (Oak Ridge National Laboratory., in the 20th century), by Oak Ridge National Laboratory. Chemical Technology Division, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, Center for Materials Science (National Measurement Laboratory). Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, and Union Carbide Corporation (page images at HathiTrust)
• Process for recovery of rhodium, palladium, and technetium from aged reprocessing wastes at Hanford (Richland, Washington : Atlantic Richfield Hanford Company, 1968., 1968), by J. Vincent Panesko, A. O. Anderson, U.S. Atomic Energy Commission, and Atlantic Richfield Hanford Company (page images at HathiTrust)
• Process for purification of fission product rhodium, palladium, and technetium recovered from aged purex supernatant wastes (Richland, Washington : Atlantic Richfield Hanford Company, 1968, 1968), by J. Vincent Panesko, A. O. Anderson, U.S. Atomic Energy Commission, and Atlantic Richfield Hanford Company (page images at HathiTrust)
• Recovery of rhodium, palladium, and technetium on strongly basic anion exchange resin (Richland, Washington : Atlantic Richfield Hanford Company, 1969., 1969), by J. Vincent Panesko, H. D. Merritt, U.S. Atomic Energy Commission, and Atlantic Richfield Hanford Company (page images at HathiTrust)
• Recovery of palladium from nuclear waste solutions using a packed column of tricapryl monomethyl ammonium chloride on an inert support (Richland, Washington : Atlantic Richfield Hanford Company, 1969., 1969), by C. A. Colvin, U.S. Atomic Energy Commission, and Atlantic Richfield Hanford Company (page images at HathiTrust)
• Recovery of Am, Cm, and Pm from Shippingport reactor fuel reprocessing wastes by successive TBP and D2EHPA extractions (Richland, Washington : Atlantic Richfield Hanford Company, 1969., 1969), by A. L. Boldt, G. L. Ritter, U.S. Atomic Energy Commission, and Atlantic Richfield Hanford Company (page images at HathiTrust)
• Rhodium recovery test : direct reduction on zinc or tin in alkaline purex wastes (Richland, Washington : Atlantic Richfield Hanford Company, 1969., 1969), by J. Vincent Panesko, H. D. Merritt, U.S. Atomic Energy Commission, and Atlantic Richfield Hanford Company (page images at HathiTrust)
• Palladium recovery from alkaline purex wastes by sorption on activated charcoal (Richland, Washington : Atlantic Richfield Hanford Company, 1970., 1970), by J. Vincent Panesko, H. D. Merritt, U.S. Atomic Energy Commission, and Atlantic Richfield Hanford Company (page images at HathiTrust)
• Anion exchange recovery of rhodium from palladium-free alkaline solutions (Richland, Washington : Atlantic Richfield Hanford Company, 1972., 1972), by J. Vincent Panesko, U.S. Atomic Energy Commission, and Atlantic Richfield Hanford Company (page images at HathiTrust)
• Application of the Hanford Thermite process to increase immobilization of in-tank solidified waste (Richland, Washington : Atlantic Richfield Hanford Company, 1972., 1972), by Michael J. Kupfer, Wallace W. Schulz, U.S. Atomic Energy Commission, and Atlantic Richfield Hanford Company (page images at HathiTrust)
• Study of the feasibility of aqueous recovery of spent fuels. Part 4, Equipment design data (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1954., 1954), by R. J. Annesser, H. A. Ohlgren, J. G. Lewis, R. J. Henig, U.S. Atomic Energy Commission, Consumers Power Company (Mich.), and University of Michigan. Engineering Research Institute (page images at HathiTrust)
• Study of the feasibility of aqueous recovery of spent fuels. Part 7, Analysis of costs and engineering evaluation of results of study (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1954., 1954), by J. G. Lewis, H. A. Ohlgren, U.S. Atomic Energy Commission, Consumers Power Company (Mich.), and University of Michigan. Engineering Research Institute (page images at HathiTrust)
• Final report, iodine chemistry, krypton solubiity, chemical processing : homogeneous reactor fuel reprocessing (West Orange, New Jersey : Vitro Laboratories, Division of Vitro Corporation of America, 1957., 1957), by Robert A. Keeler, Raymond M. Chappel, Stanley J. Klach, Charles J. Anderson, Vitro Corporation, U.S. Atomic Energy Commission, and Union Carbide Nuclear Company (page images at HathiTrust)
• A model of iodine transport and reaction kinetics in a nuclear fuel reprocessing plant (Oak Ridge, Tennessee : Oak Ridge National Laboratory, Chemical Technology Division, 1977., 1977), by W. Davis, Oak Ridge National Laboratory. Chemical Technology Division, and U.S. Nuclear Regulatory Commission. Office of Nuclear Material Safety and Safeguards (page images at HathiTrust)
• Quarterly progress report on fission product behavior in LWRs for the period ... (Oak Ridge, Tennessee : Oak Ridge National Laboratory, Chemical Technology Division., 1978), by Oak Ridge National Laboratory. Chemical Technology Division and Fuel Cycle U.S. Nuclear Regulatory Commission. Division of Safeguards (page images at HathiTrust)
• Nuclear decay data for radionuclides occurring in routine releases from nuclear fuel facilities (Oak Ridge, Tennessee : Oak Ridge National Laboratory, Health and Safety Research Division, 1977., 1977), by David C. Kocher, Fuel Cycle U.S. Nuclear Regulatory Commission. Division of Safeguards, and Oak Ridge National Laboratory. Health and Safety Research Division (page images at HathiTrust)
• GESMO ([Washington, DC] : U.S. Atomic Energy Commission, 1974., 1974), by U.S. Atomic Energy Commission (page images at HathiTrust)
• Proceedings ... v. 1-16. (United Nations, 1955), by Switzerland) International Conference on the Peaceful Uses of Atomic Energy (1955 : Geneva (page images at HathiTrust; US access only)

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