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Zirconium alloys -- Corrosion

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• Zirconium alloys
• Corrosion

• Zirconium alloys -- Corrosion -- Testing
• Niobium-zirconium alloys -- Corrosion
• Zircaloy-2 -- Corrosion

• High-temperature enthalpy and x-ray powder diffraction data for ZrI4 (U.S. Dept. of the Interior, Bureau of Mines, 1980), by M. J. Ferrante and R. A. McCune (page images at HathiTrust)
• Effects of aluminum, nitrogen, manganese, and copper impurities on hot water and steam corrosion rates of zircaloy-3 (U.S. Dept. of the Interior, Bureau of Mines, 1961), by M. D. Carver, H. Kato, Richard F. Link, and United States Bureau of Mines (page images at HathiTrust)
• Heat treatment, tensile properties, and corrosion resistance of Zr-2 a/o NB-2 a/o Sn alloy (Hanford Atomic Products Operation, 1961), by J. J. Holmes, U.S. Atomic Energy Commission, Hanford Atomic Products Operation, and Pacific Northwest Laboratory (page images at HathiTrust)
• Autoclave testing of zircaloy-2 (U.S. Atomic Energy Commission, 1960), by R. A. Thiede, 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. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
• Recovery and recrystallization of zirconium and its alloys. Part 4, Corrosion behavior (Hanford Atomic Products Operation, 1961), by Spencer Harrison Bush, D. L. Gray, R. S. Kemper, 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. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
• Development of corrosion-resistant aluminum alloys for high-temperature water service (Hanford Atomic Products Operation, 1961), by H. C. Bowen, 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)
• Multiple rate transitions in the aqueous corrosion of zircaloy (U.S. Atomic Energy Commission, 1960), by B. Griggs, D. W. Shannon, H. P. Maffei, 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 of uranium-zirconium alloys in water at temperatures up to 100 C (U.S. Atomic Energy Commission, Technical Information Service Extension, 1957), by H. A. Pray, Warren E. Berry, Battelle Memorial Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Hydrogen pickup during corrosion of zirconium alloys (Battelle Memorial Institute ;, 1959), by Warren E. Berry, Earl L. White, D. A. Vaughan, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Zircaloy-4 corrosion in halide solutions and at crevices in high-temperature water (Battelle Memorial Institute ;, 1962), by Warren E. Berry, Frederick W. Fink, Earl L. White, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Corrosion mechanism of zirconium and its alloys : diffusion of oxygen in zirconium dioxide (U.S. Atomic Energy Commission, Division of Technical Information, 1962), by D. L. Douglass, Joint U.S.-Euratom Research and Development Program, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Investigations of binary zirconium alloys (Knolls Atomic Power Laboratory, General Electric Company, 1960), by A. E. Bibb, D. L. Douglass, A. P. Beard, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• Beneficial effect of alloy additions to zirconium on the corrosion resistance in 600°F water (Oak Ridge, Tenn. : United States Atomic Energy Commission, Technical Information Service, 1952., 1952), by D. S. Kneppel, T. T. Magel, Massachusetts Institute of Technology, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Corrosion of zirconium alloys in 900° steam (Oak Ridge, Tennessee : United States Atomic Energy Commission, Office of Technical Information, 1958., 1958), by J. Paul Pemsler, Inc Nuclear Metals, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Corrosion of zirconium alloys in 900 and 1000° steam (Oak Ridge, Tennessee : United States Atomic Energy Commission, Office of Technical Information, 1960., 1960), by J. Paul Pemsler, Inc Nuclear Metals, and U.S. Atomic Energy Commission (page images at HathiTrust)
• The corrosion of zircaloy base fuel alloys in high temperature water (Washington, D.C. : Office of Technical Services, Department of Commerce, 1958., 1958), by Stanley Kass, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• High-temperature water and steam-corrosion behavior of zirconium-uranium alloys (Washington, D.C. : Office of Technical Services, Department of Commerce, 1959., 1959), by Stanley Kass, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• The effect of lithium hydroxide and related solutions on the corrosion rate of zircalloy in 680 F water (Washington, D.C. : Office of Technical Services, Department of Commerce, 1962., 1962), by E. Hillner, J. N. Chirigos, Westinghouse Electric Corporation, United States. Department of Commerce. Office of Technical Services, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Corrosion studies of ternary zirconium alloys in high-temperature water and steam (Argonne National Laboratory, Metallurgy Division, 1961), by R. D. Misch, C. Van Drunen, and Argonne National Laboratory (page images at HathiTrust)
• Operations Division (Oak Ridge National Laboratory, 1962), by G. H. Jenks, E. G. Bohlmann, J. E. Baker, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)

• Corrosion testing of Zircaloy-2 and Zircaloy-3 (Washington, D.C. : Office of Technical Services, Department of Commerce, 1957., 1957), by Stanley Kass, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Pickling of the zircaloys prior to corrosion exposure (Washington, D.C. : Office of Technical Services, Department of Commerce, 1958., 1958), by Stanley Kass, D.B. Scott, A.E. Oaks, D.J. Fontanese, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)

• Evaluation of zirconium 1.5 without niobium cladding for use in boiling water reactor environments (U.S. Atomic Energy Commission, Division of Technical Information, 1962), by W. C. Rous, C. J. Baroch, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust)

• The physical integrity and corrosion resistance of the zircaloy-2 pressure tubes for the PRTR (U.S. Atomic Energy Commission, 1960), by R. L. Knecht, 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)
• Reaction kinetics of zirconium and zircaloy-2 in dry air at elevated temperatures (Hanford Atomic Products Operation, 1955), by L. F. Kendall, General Electric Company, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
• A visual study of the corrosion of defected zircaloy-2-clad fuel specimens by hot water (Battelle Memorial Institute ;, 1959), by Elmer F. Stephan, Frederick W. Fink, P. D. Miller, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Effect of additions to zircaloy on hydrogen pickup during aqueous corrosion (Battelle Memorial Institute ;, 1959), by Warren E. Berry, Frederick W. Fink, Earl L. White, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Creep and corrosion properties of zircaloy-2 in steam at 750 F (Battelle Memorial Institute ;, 1960), by Edward J. Jablonowski, Frederic R. Shober, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Microprobe study of zircaloy corrosion films (E.I. du Pont de Nemours & Co., Savannah River Laboratory, 1964), by Kurt F. J. Heinrich, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Effect of welding atmosphere and pickling on the corrosion resistance of welded zircaloy-2 and -3 (Knolls Atomic Power Laboratory, General Electric Company, 1957), by K.H. Koopman, A.P. Jordan, Toftegaard,S.A., A.B. Riedinger, W.S. Horton, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• Corrosion of the zircaloy-2 - niobium couple (Knolls Atomic Power Laboratory, General Electric Company, 1960), by R. E. Campagnoni, M. A. Powers, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• Interdiffusion in zircaloy-2 clad U-2 w/o Zr fuel materials and its effect upon corrosion behavior (Oak Ridge, Tennessee : United States Atomic Energy Commission, Office of Technical Information, 1960., 1960), by A. L. Geary, Inc Nuclear Metals, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Effects of silicon, nitrogen, and oxygen on the corrosion and hydrogen absorption performance of zircaloy-2 (Available from the Office of Technical Services, Dept. of Commerce, 1963), by S. Kass, F. L. Shubert, J. D. Grozier, Westinghouse Electric Corporation, Bettis Atomic Power Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• A summary of the work associated with the solution and understanding of stringer-type corrosion in Zircaloy-2 and -3 (Pittsburgh, Pennsylvania : Bettis Plant, 1959., 1959), by J. G. Goodwin, F. L. Shubert, J. D. Grozier, L. W. Rubenstein, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Effect of surface treatment on the corrosion resistance of zircaloy-2 (Washington, D.C. : Office of Technical Services, Department of Commerce, 1961., 1961), by D. B. Scott, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Corrosion of zircaloy-2 in steam containing fluoride-ion additions (San Jose, California : General Electric Company, Atomic Power Equipment Department, Vallecitos Atomic Laboratory, 1963., 1963), by R. S. Young, Vallecitos Atomic Laboratory, U.S. Atomic Energy Commission, and General Electric Company. Atomic Power Equipment Department (page images at HathiTrust)
• Reactor Chemistry Division (Oak Ridge National Laboratory, 1962), by G. H. Jenks, J. E. Baker, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Corrosion of zircaloy in crevices under nucleate boiling conditions (Knolls Atomic Power Laboratory, General Electric Company, 1962), by W. Kermit Anderson, M. J. McGoff, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)

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

• Properties of reactor fuel rod materials at high temperatures : final summary report : severe core damage property tests program (The Commission, 1987), by J. T. Prater, E. L. Courtright, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Reactor Accident Analysis (page images at HathiTrust)
• Evaluating strength and ductility of irradiated zircaloy, task 5 : quarterly progress report, April-June 1978 (The Commission, 1978), by L. M. Lowry, Battelle Memorial Institute. Columbus Laboratories, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
• Evaluating strength and ductility of irradiated zircaloy task 5 : progress report July - December 1978 (The Commission, 1980), by L. M. Lowry, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Battelle Memorial Institute. Columbus Laboratories (page images at HathiTrust)
• Evaluating strength and ductility of irradiated zircaloy task 5 : quarterly progress report January-March, 1979 (The Commission, 1979), by L. M. Lowry, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Battelle Memorial Institute. Columbus Laboratories (page images at HathiTrust)
• Evaluating strength and ductility of irradiated zircaloy task 5 : quarterly progress report April - June, 1979 (The Commission, 1980), by L. M. Lowry, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Battelle Memorial Institute. Columbus Laboratories (page images at HathiTrust)
• Evaluating strength and ductility of irradiated zircaloy task 5 : quarterly progress report July - September 1979 (The Commission, 1980), by L. M. Lowry, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Battelle Memorial Institute. Columbus Laboratories (page images at HathiTrust)
• Anodizing as a means of evaluating the corrosion resistance of zirconium and zirconium alloys (U.S. Atomic Energy Commission, 1953), by R. D. Misch, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
• A report on some attempts to cast centrifugally fuel elements of small diameter (Argonne National Laboratory, Metallurgy Division, 1961), by F. L. Yaggee, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
• A preliminary survey of zirconium alloys (U.S. Dept. of the Interior, Bureau of Mines, 1950), by W. J. Kroll, A. H. Roberson, E. T. Hayes, and C. T. Anderson (page images at HathiTrust)
• Corrosion properties of the TZM and molybdenum-30 tungsten alloys (U.S. Dept. of the Interior, Bureau of Mines, 1968), by Walter L. Acherman, David Schlain, J. P. Carter, and United States Bureau of Mines (page images at HathiTrust)
• Determination of a part of the magnesium-zirconium liquidus (U.S. Dept. of the Interior, Bureau of Mines, 1965), by R. L. Crosby, K. A. Fowler, and United States Bureau of Mines (page images at HathiTrust)
• Zirconium-dysprosium equilibrium diagram (U.S. Dept. of the Interior, Bureau of Mines, 1960), by Jack G. Croeni, H. Kato, and C. E. Armantrout (page images at HathiTrust)
• Zirconium-gadolinium equilibrium diagram (U.S. Dept. of the Interior, Bureau of Mines, 1961), by Mark I. Copeland, H. Kato, and Clo E. Armantrout (page images at HathiTrust)
• Effect of impurity levels on zircaloy 2 microstructure, mechanical properties, and corrosion rates (U.S. Dept. of the Interior, Bureau of Mines, 1964), by Haruo Kat©Æo, M. D. Carver, and D. J. Stoops (page images at HathiTrust)
• A preliminary study of the aging behavior of wrought columbium-1% zirconium alloys (Oak Ridge National Laboratory, 1961), by David O. Hobson and U.S. Atomic Energy Commission (page images at HathiTrust)
• Heat treatment, tensile properties, and corrosion resistance of Zr-2 a/o NB-2 a/o Sn alloy (Hanford Atomic Products Operation, 1961), by J. J. Holmes, U.S. Atomic Energy Commission, Hanford Atomic Products Operation, and Pacific Northwest Laboratory (page images at HathiTrust)
• Investigation of pyrolytic graphite as crucible material for zirconium melting (Hanford Atomic Products Operation, 1962), by R. E. Westerman, U.S. Atomic Energy Commission, Hanford Atomic Products Operation Reactor and Fuels Research and Development Operation, and Pacific Northwest Laboratory (page images at HathiTrust)
• Fabrication and evaluation of zircaloy-2 and zircaloy-4 tubing for use in cladding uranium dioxide and aluminum-plutonium fuel (U.S. Atomic Energy Commission, 1960), by P. L. Farnsworth, K. M. Haws, 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. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
• Evaluation of welded and seamless zirconium and zircaloy-2 tubing : final report (U.S. Atomic Energy Commission, 1958), by S. H. Bush, 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. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
• Zircaloy welding techniques deeloped for plutonium recycle program UO₂ fuel element fabrication (U.S. Atomic Energy Commission, 1960), by L. E. Mills, 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. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
• The zirflex process : terminal development report (U.S. Atomic Energy Commission, 1960), by P. W. Smith, 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 (page images at HathiTrust)
• Recovery and recrystallization of zirconium and its alloys. Part 2, Annealing of cold-worked zirconium (Hanford Atomic Products Operation, 1961), by D. L. Gray, 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. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
• Recovery and recrystallization of zirconium and its alloys. Part 1, Specimen compositions, cold working, heat treatment, and survey of the literature (Hanford Atomic Products Operation, 1961), by S. H. Bush, D. L. Gray, R. S. Kemper, 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. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
• Recovery and recrystallization of zirconium and its alloys. Part 3, Annealing effects in zircaloy-2 and zircaloy-3 (Hanford Atomic Products Operation, 1961), by Spencer Harrison Bush, R. S. Kemper, 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. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
• Annealing of warm-extruded zircaloy-2 to an ultrafine grain size (Hanford Atomic Products Operation, 1961), by R. L. Knecht, 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. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
• Mechanisms and kinetics of uranium corrosion and uranium core fuel element ruptures in water and steam (U.S. Atomic Energy Commission, 1960), by V. H. Troutner, 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)
• Temperature distributions of reactor fuel element end caps (U.S. Atomic Energy Commission, 1961), by K. R. Merckx, 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)
• Extrusion characteristics of uranium-zirconium and uranium-carbon alloys (U.S. Atomic Energy Commission, 1961), by J. C. Tverberg, J. J. Holmes, 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. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
• A study of the short time annealing of cold worked zirconium (Hanford Atomic Products Operation, 1956), by D. E. Johnson, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
• Phase diagram studies of zirconium with silver, indium, and antimony (Oak Ridge National Laboratory, 1957), by J. O. Jr Betterton, D. S. Easton, J. H. Jr Frye, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory Metallurgy Division (page images at HathiTrust)
• Calorimetric investigation of zirconium, titanium, and zirconium alloys from 60 to 960⁰ degrees C (Oak Ridge National Laboratory, 1957), by J. L. Scott, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory Metallurgy Division (page images at HathiTrust)
• Anodizing as a metallographic technique for zirconium base alloys (Oak Ridge National Laboratory, 1957), by M. L. Picklesimer, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory Metallurgy Divison (page images at HathiTrust)
• Summary report : an evaluation of the substitution of zircaloy for stainless steel in N.S. Savannah fuel-element containers (Oak Ridge National Laboratory, 1963), by C. L. Whitmash, L. R. Shobe, L. D. Schaffer, H. C. McCurdy, E. E. Gross, T. D. Anderson, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Reactor Division (page images at HathiTrust)
• Preliminary x-ray investigations of the hydrates of zirconium tetrafluoride (Idaho Operations Office, U.S. Atomic Energy Commission, 1958), by R. L. Wells, 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)
• 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)
• 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)
• 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)
• 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)
• Constitution diagram of the antimony-zirconium alloy system (U.S. Atomic Energy Commission, Technical Information Service, 1954), by R. F. Russi, H. A. Wilhelm, Ames Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Allotropic transformations in titanium, zirconium, and uranium alloys (U.S. Atomic Energy Commission, Technical Information Service, 1955), by A. E. Dwight, Argonne National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• The anodic oxidation of some dilute binary zirconium alloys (United States Atomic Energy Commission, Technical Information Service Extension, 1957), by G. B. Adams, Pierre van Rysselberghe, Curtis E. Borchers, U.S. Atomic Energy Commission, and University of Oregon (page images at HathiTrust)
• Scaling of zirconium and zirconium alloys (U.S. Atomic Energy Commission. Technical Information Service Extension, 1957), by J. A. Burka, R. E. Swift, C. S. Crouse, University of Kentucky Kentucky Research Foundation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Evaluation of materials of construction for the Sulfex and Zirflex processes (Brookhaven National Laboratory, 1962), by Herbert M. Katz, Robert Isler, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
• Studies on the anodic polarization of zirconium and zirconium alloys (U.S. Atomic Energy Commission, Technical Information Service, 1953), by Mario Maraghini, Pierre Van Rysselberghe, Geroge B. Adams, U.S. Atomic Energy Commission, and University of Oregeon (page images at HathiTrust)
• Development of zirconium alloys. Part I (U.S. Atomic Energy Commission, Technical Information Service, 1955), by A. D. Schwope, Walston Chubb, L. L. Marsh, Battelle Memorial Institute, and U.S. Atomic Energy Commission. Technical Information Service (page images at HathiTrust)
• Development of zirconium alloys. Part II (U.S. Atomic Energy Commission, Technical Information Service, 1955), by A. D. Schwope, Walston Chubb, Battelle Memorial Institute, and U.S. Atomic Energy Commission. Technical Information Service (page images at HathiTrust)
• Kinetics of the zirconium-nitrogen and zirconium-tin-nitrogen systems (United States Atomic Energy Commission, Technical Information Service, 1955), by Manley William Mallett, B. B. Cleland, J. Belle, Battelle Memorial Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Processing of uranium-zirconium alloys (United States Atomic Energy Commission, Technical Information Service Extension, 1957), by S. J. Paprocki, R. F. Dickerson, Henry A. Saller, J. H. Jackson, John George Kura, J. W. Holladay, Battelle Memorial Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
• A high strength zirconium alloy : zirconium - 4 w/o tin - 1.6 w/o molybdenum (U.S. Atomic Energy Commission, Technical Information Service, 1955), by Walston Chubb, G. K. Manning, G. T. Muehlenkamp, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Phase relations in the uranium-zirconium-oxygen systems involving zirconium and uranium dioxide (U.S. Atomic Energy Commission, Technical Information Service, 1956), by J. Robert Doig, Arthur A. Bauer, Joseph M. Fackelmann, Frank A. Rough, Henry A. Saller, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• The reaction of steam with uranium and with various uranium-niobium-zirconium alloys at high temperatures (Battelle Memorial Institute, 1957), by Alexis W. Lemmon, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Vapor pressures of the rubidium fluoride-zirconium fluoride and lithium fluoride-zirconium fluoride systems (Battelle Memorial Institute, 1957), by Karl A. Sense, Robert B. Filbert, Richard W. Stone, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Joining zircaloy-stainless steel and SAP alloys by friction, rolling and explosive techniques (Battelle Memorial Institute ;, 1962), by Ronald J. Carlson, Stanley W. Porembka, Stan J. Paprocki, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Investigation of the yield phenomenon in Zircaloy-2 at elevated temperatures (Battelle Memorial Institute ;, 1963), by Ronald F. Dickerson, Maurice F. Amateau, Arthur P. Young, Paul B. Shumaker, Ralph W. Getz, Frederic R. Shober, Battelle Memorial Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Effect of high boron burnups on B₄C and ZrB₂ dispersions in Al₂O₃ and Zircaloy-2 (Battelle Memorial Institute ;, 1963), by Richard J. Burian, John E. Gates, Earle Fromm, Battelle Memorial Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Joining of zircaloy and inconel 600 tubes by explosive welding (Battelle Memorial Institute, 1965), by Ronald J. Carlson, Charles C. Simons, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Total optical emissivity and electrical resistivity of (U₀₃Zr₀-- )C in the temperature range 1400°K to 2800°K (Los Alamos Scientific Laboratory of the University of California, 1963), by L. D. Tatro, L. W. Miller, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Tensile properties of yttrium-titanium and yttrium-zirconium alloys (Ames Laboratory, 1960), by D. W. Bare, O. N. Carlson, E. D. Gibson, U.S. Atomic Energy Commission, and Ames Laboratory (page images at HathiTrust)
• Vapor pressures of the sodium fluoride-zirconium fluoride system and derived information : errata page (Battelle Memorial Institute, 1956), by Karl A. Sense, U.S. Atomic Energy Commission, and Battelle Memorial Institute (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)
• Nondestructive test station for zircaloy-clad reactor fuel (E.I. du Pont de Nemours & Company, Savannah River Laboratory, 1963), by Leslie E. Goodwin, Herbert D. Hendricks, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Measurement of preferred orientation of thin-walled zircaloy-2 tubes (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1961), by Edward F. Sturcken, W. G. Duke, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Evaluation of tandem-extruded joints between zircaloy and stainless steel (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1962), by J. Walter Joseph, F. C. Apple, U.S. Atomic Energy Commission, and Savannah River Laboratory (page images at HathiTrust)
• Proceedings of the USAEC symposium on zirconium alloy development, Castlewood, Pleasanton, California, November 12-14, 1962 (Vallecitos Atomic Laboratory, General Electric, Atomic Power Equipment Dept., 1962), by Calif.) USAEC Symposium on Zirconium Alloy Development (1962 : Pleasonton, Harold Holmes Klepfer, Vallecitos Atomic Laboratory, and Joint U.S.-Euratom Research and Development Program (page images at HathiTrust)
• Design and fabrication of fuel rods clad with stainless-steel-lined zircaloy-2 (U.S. Atomic Energy Commission, Division of Technical Information, 1964), by C. J. Baroch, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Thermal-stress-fatigue behavior of zirconium and zirconium alloys : final report (U.S. Atomic Energy Commission, Division of Technical Information, 1961), by K. E. Horton, R. S. Stewart, U.S. Atomic Energy Commission. Division of Technical Information, U.S. Atomic Energy Commission. Division of Reactor Development, and Advanced Technology Laboratories (page images at HathiTrust)
• Chemical base coatings for zirconium and zircaloy (U.S. Atomic Energy Commission, Technical Information Service Extension, 1956), by E. J. Hennessey, A. Grella, U.S. Atomic Energy Commission, and Bridgeport Brass Company (page images at HathiTrust)
• Preparation of nuclear poison and control alloys : zirconium base - boron alloys (Knolls Atomic Power Laboratory, General Electric Company, 1957), by A. P. Beard, W. B. Clark, J. W. Harrison, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• Production of molybdenum-uranium and zirconium-uranium alloys (Union Carbide Nuclear Company, Paducah Plant ;, 1960), by C. W. Loveland, J. E. Owens, Carbide and Carbon Chemicals Corporation, Union Carbide Nuclear Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• The thermal analysis of zirconium - tin alloys (Knolls Atomic Power Laboratory, 1952), by L. L. Wyman, J. F. Bradley, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Theoretical kinetics and stresses for delta-phase isothermal hydriding of uranium-zirconium (Atomics International, 1962), by M. E. Nathan, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Fabrication and welding characteristics of high strength zirconium alloy 3Z1 (Atomics International, 1961), by R. K. Wagner, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• High-strength zirconium alloys (Atomics International, 1959), by R. K. Wagner, H. E. Kline, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Explosions occurring during chemical etching or pickling of uranium-zirconium alloys (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Technical Information Service, 1952., 1952), by H. P. Roth, Massachusetts Institute of Technology, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Rapid pulse heating of modified zirconium-uranium hydrides to destruction : (final report) (Atomics International, 1965), by R. A. Finch, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• The chemical analysis of zirconium and zircaloy metals (Oak Ridge, Tennessee : United States Atomic Energy Commission, Office of Technical Information, 1957., 1957), by E. B. Read, H.M. Read, Inc Nuclear Metals, and U.S. Atomic Energy Commission (page images at HathiTrust)
• The cold working of extruded zircaloy tubing (Oak Ridge, Tennessee : United States Atomic Energy Commission, Office of Technical Information, 1958., 1958), by N. R. Gardner, P. Loewenstein, Inc Nuclear Metals, and U.S. Atomic Energy Commission (page images at HathiTrust)
• High strength zirconium-base alloys (Oak Ridge, Tennessee : United States Atomic Energy Commission, Office of Technical Information, 1961., 1961), by G. A. Henrikson, Inc Nuclear Metals, and U.S. Atomic Energy Commission (page images at HathiTrust)
• The constitution of delta-phase alloys of the system uranium-zirconium-titanium (Columbus, Ohio : Battelle Memorial Institute, 1955., 1955), by Henry A. Saller, J.Robert Doig, Arthur A. Bauer, Frank A. Rough, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Vapor pressures of the sodium fluoride-zirconium fluoride system and derived information (Columbus, Ohio : Battelle Memorial Institute, 1956., 1956), by Karl A. Sense, Robert B. Filbert, M. Jack Snyder, Richard W. Stone, Richard E. Bowman, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• The physical properties of sintered zirconium (Washington, D.C. : Office of Technical Services, Department of Commerce, 1951., 1951), by Herbert S. Kalish, Roswell P. Angier, Henry H. Hausner, Inc Sylvania Electric Products, and U.S. Atomic Energy Commission (page images at HathiTrust)
• The powder metallurgy of zirconium-tin alloys. Part I (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service, 1952., 1952), by Henry H. Hausner, Richard M. Treco, Inc Sylvania Electric Products, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Recrystallization and grain growth characteristics in zirconium and zirconium-tin alloys (Oak Ridge, Tennessee : U.S. Atomic Energy Commission, Technical Information Service, 1953., 1953), by Fred D. Rosi, F. C. Perkins, Inc Sylvania Electric Products, and U.S. Atomic Energy Commission (page images at HathiTrust)
• The transformation kinetics of uranium-zirconium alloys containing 50 and 60 WT PCT uranium (Washington, D.C. : Office of Technical Services, Department of Commerce, 1956., 1956), by John J. Kearns, Westinghouse Electric Corporation, Bettis Atomic Power Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Ex-reactor determination of thermal gap and contact conductance between uranium dioxide, zircaloy-4 interfaces : stage I low gas pressure ([Washington, D.C.] : U.S. Nuclear Regulatory Commission ; [1979]., 1979), by John E. Garnier, Stefan Begej, Pacific Northwest Laboratory. Materials Department. Ceramics and Graphite Section, United States. Department of Energy, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• Evaluating strength and ductility of irradiated zircaloy task 5 : quarterly progress report April - June, 1978 (Washington, D.C. : Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Reactor Safety Research, 1975-, 1975), by L. M. Lowry, W. J. Gallagher, A. J. Markworth, J. S. Perrin, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Battelle Memorial Institute. Columbus Laboratories (page images at HathiTrust)
• Evaluating strength and ductility of irradiated zircaloy, task 5 : quarterly progress report January-March, 1978 (The Commission ;, 1978), by A. A. Bauėr, A. J. Markworth, W. J. Gallagher, J. M. Lowry, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Battelle Memorial Institute. Columbus Laboratories (page images at HathiTrust)
• Plutonium 238 isotopic fuel form data sheets. (Miamisburg, Ohio : Mound Laboratory, 1969., 1969), by S. G. Abrahamson, D. G. Silver, D. R. Rogers, W. H. Smith, B. R. Kokenge, D. G. Carfagno, Monsanto Chemical Company, Mound Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)

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