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Zirconium-vanadium alloys

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• Vanadium alloys
• Zirconium alloys

• Tensile properties of zirconium and zirconium alloys. (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Technical Information Service, 1955.), by C. R. Simcoe, W. L. Mudge, Westinghouse Electric Corporation. Atomic Power Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Hydrogen overvoltage and electrochemical potentials of zirconium and zirconium intermetallics / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Division of Technical Information, 1963), by J. S. Armijo, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)

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

• Preliminary investigation of effect of environmental factors on salt stress corrosion cracking of Ti-8Al-lMO-lV at elevated temperatures / (Washington, D.C. : National Aeronautics and Space Administration ; Washington, D.C. : For sale by the Office of Technical Services, Department of Commerce [distributor], 1964), by D. N. Braski and Langley Research Center (page images at HathiTrust)
• The effect of composition on the mechanism of stress-corrosion cracking of titanium alloys in N2O4, and aqueous and hot-salt environments / (Washington, D.C. : National Aeronautics and Space Administration ; Springfield, Va. : For sale by the Clearinghouse for Federal Scientific and Technical Information [distributor], 1970), by J. D. Boyd, United States National Aeronautics and Space Administration, and Battelle Memorial Institute (page images at HathiTrust)
• Effect of decarburization on notch sensitivity and fatigue-crack-propagation rates in 12 MoV stainless-steel sheet / (Washington, [D.C.] : National Aeronautics and Space Administration, 1961), by William H. Herrnstein, A. J. McEvily, United States National Aeronautics and Space Administration, and Langley Research Center (page images at HathiTrust)
• Elevated temperature dynamic moduli of vanadium titanium and V-Ti alloys (Wright-Patterson Air Force Base, Ohio, Wright Air Development Division, Air Research and Development Command, U. S. Air Force, 1960), by W. H. Hill and B. A. Wilcox (page images at HathiTrust)
• Mechanical properties, oxidation characteristics, and weldability of two uncoated and coated vanadium-base alloys / (Washington, D.C. : National Aeronautics and Space Administration ; [For sale by the Office of Technical Services, Department of Commerce, Washington, D.C. 20230], 1965), by Dick M. Royster, Cynthia A. Dysleski, Charles R. Manning, Langley Research Center, and United States National Aeronautics and Space Administration (page images at HathiTrust; US access only)
• Properties of vanadium-base tungsten and chromium alloys / ([Washington, D.C.] : U.S. Dept. Of the Interior, Bureau of Mines, 1967), by David R. Mathews, Henry G. Iverson, and United States Bureau of Mines (page images at HathiTrust)
• The thorium-vanadium system / (Oak Ridge, Tenn., U.S. Atomic Energy Commission. Technical Information Service, 1953), by H. L. Levingston, B. A. Rogers, Ames Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Interactions of titanium and molybdenum additions with interstitial impurities in vanadium / ([Washington, D.C.] : U.S. Dept. of the Interior, Bureau of Mines, [1969]), by George H. Keith and United States Bureau of Mines (page images at HathiTrust)
• Reaction of C₀-Ni-V alloys with O₂ at 1,351⁰ to 1,429⁰K / ([Washington, D.C.] : U.S. Dept. of Interior, Bureau of Mines, [1970]), by Robert M. Doerr, J. W. Jensen, and United States Bureau of Mines (page images at HathiTrust)
• Development of high-temperature vanadium-base alloy / ([Washington, D.C.] : U.S. Dept. of Interior, Bureau of Mines, [1970]), by George H. Keith, J. S. Winston, and United States Bureau of Mines (page images at HathiTrust)
• Stress corrosion cracking of vanadium, molybdenum, and a titanium-vanadium alloy / ([Washington, D.C.] : U.S. Dept. of the Interior, Bureau of Mines, 1965), by J. P. Carter, David Schlain, Charles B. Kenahan, and United States Bureau of Mines (page images at HathiTrust)
• Properties of vanadium-carbon alloys / ([Washington, D.C.] : U.S. Dept. of the Interior, Bureau of Mines, 1965), by David R. Mathews, E. A. Rowe, and United States Bureau of Mines (page images at HathiTrust)
• Heats of formation of goethite, ferrous vanadate, and manganese molybdate / ([Washington, D.C.] : U.S. Dept. of the Interior, Bureau of Mines, 1965), by Ronald Barany and United States Bureau of Mines (page images at HathiTrust)
• Corrosion properties of molybdenum, tungsten, vanadium, and some vanadium alloys / ([Washington, D.C.] : U.S. Dept. of the Interior, Bureau of Mines, 1966), by David Schlain, C. B. Kenahan, J. P. Carter, Walter L. Acherman, and United States Bureau of Mines (page images at HathiTrust)
• Columbium-vanadium binary alloys for high-temperature service / (Washington, D.C. : U.S. Dept. of the Interior, Bureau of Mines, 1962), by Herbert R. Babitzke (page images at HathiTrust)
• The self-diffusion of iron in delta iron / (Livermore, CA : University of California Lawrence Radiation Laboratory, 1962), by Richard J. Borg, Oscar Krikorian, David Y. F. Lai, Lawrence Radiation Laboratory, and Lawrence Livermore Laboratory (page images at HathiTrust)
• Diffusion in body-centered cubic metals zirconium, vanadium, niobium, and tantalum / (Oak Ridge, Tenn., Oak Ridge National Laboratory, 1964), by Ted Sadler Lundy and U.S. Atomic Energy Commission (page images at HathiTrust)
• Vanadium-chromium alloy system / ([Ames, Iowa] : Ames Laboratory, [1959]), by O. N. Carlson, A. L. Eustice, U.S. Atomic Energy Commission, and Ames Laboratory (page images at HathiTrust)
• Electrical, thermoelectric, hardness, and corrosion properties of vanadium-base alloys /, by H. J. Cleary, Inc Nuclear Metals, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Vanadium-oxygen solid solutions /, by A. U. Seybolt, H. T. Sumsion, Knolls Atomic Power Laboratory, General Electric Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Improvements in consolidation and fabrication of vanadium-20 w/o titanium(TV-20) /, by W. R. Burt, R. M. Mayfield, F. J. Karasek, W. C. Kramer, and Argonne National Laboratory (page images at HathiTrust)
• Quarterly technical progress report : fuels, materials, and coolant chemistry programs, January-March 1970 /, by Rockwell International. Atomics International Division and U.S. Atomic Energy Commission (page images at HathiTrust)
• Phase relationships in selected binary and ternary vanadium-base alloys systems /, by Steven A. Komjathy, William Rostoker, Robert H. Read, issuing body Wright Air Development Center, sponsor Armour Research Foundation (U.S.), and sponsor United States. Air Force. Air Research and Development Command (page images at HathiTrust)

• Summary of trade and tariff information : ferroalloys : TSUS items 606.20-606.53 / (Washington, D.C. : U.S. International Trade Commission, [1983]), by Laszlo Boszormenyi and United States International Trade Commission (page images at HathiTrust)

• Development of the weld-braze joining process / (Washington, D.C. : National Aeronautics and Space Administration ; [Springfield, Va. : For sale by the National Technical Information Service], 1973), by Thomas T. Bales, Winfrey E. Arnold, Dick M. Royster, and Langley Research Center (page images at HathiTrust)
• Hot press and roll welding of titanium-6-percent-aluminum-4-percent-vanadium bar and sheet with auto-vacuum cleaning / (Washington, D.C. : National Aeronautics and Space Administration ; [Springfield, Va. : For sale by the National Technical Information Service], 1972), by Kenneth H. Holko and Lewis Research Center (page images at HathiTrust)
• The stress corrosion susceptibility of several alloys in hydrazine fuels / (Washington, D.C. : National Aeronautics and Space Administration ; [Springfield, Va. : For sale by the National Technical Information Service], 1974), by William Gilbreath, Michael J. Adamson, and Ames Research Center (page images at HathiTrust)
• Fatigue-test acceleration with flight-by-flight loading and heating to simulate supersonic-transport operation / (Washington, D.C. : National Aeronautics and Space Administration ; [Springfield, Va. : For sale by the National Technical Information Service], 1973), by L. A. Imig, L. E. Garrett, and Langley Research Center (page images at HathiTrust)
• Oxidation characteristics of Ti-25Al-10Nb-3V-1Mo intermetallic alloy / (Washington, D.C. : National Aeronautics and Space Administration, Office of Management, Scientific and Technical Information Division ; Springfield, Va. : For sale by the National Technical Information Service, 1990), by Terryl A. Wallace and Langley Research Center (page images at HathiTrust)
• Effect of outdoor exposure at ambient and elevated temperatures on fatigue life of Ti-6Al-4V titanium alloy sheet in the annealed and the solution-treated and aged condition / (Washington, D.C. : National Aeronautics and Space Administration ; [Springfield, Va. : For sale by the National Technical Information Service], 1974), by Edward P. Phillips and Langley Research Center (page images at HathiTrust)
• Load interaction effects on fatigue crack growth in Ti-6Al-4V alloy / (Washington, D.C. : National Aeronautics and Space Administration ; [Springfield, Va. : For sale by the National Technical Information Service], 1973), by Robert Peh-ying Wei, J. H. FitzGerald, T. T. Shih, Langley Research Center, and Lehigh University (page images at HathiTrust)
• A study of crack closure in fatigue / (Washington, D.C. : National Aeronautics and Space Administration ; [Springfield, Va. : For sale by the National Technical Information Service], 1973), by T. T. Shih, Robert Peh-ying Wei, Langley Research Center, and Lehigh University (page images at HathiTrust)
• Crack-closure and crack-growth measurements in surface-flawed titanium alloy Ti-6Al-4V / (Washington, D.C. : National Aeronautics and Space Administration ; [Springfield, Va. : For sale by the National Technical Information Service], 1975), by Elber Wolf and Langley Research Center (page images at HathiTrust)
• Growth of surface and corner cracks in beta-processed and mill-annealed Ti-6Al-4V / (Washington, D.C. : National Aeronautics and Space Administration ; [Springfield, Va. : For sale by the National Technical Information Service], 1975), by Paul D. Bell and Langley Research Center (page images at HathiTrust)
• Equipment and procedures for glass-bead peening titanium-alloy tanks / (Washington, D.C. : National Aeronautics and Space Administration ; Springfield, Va. : For sale by the Clearinghouse for Federal Scientific and Technical Information, [1968]), by Thomas T. Bales, W. Barry Lisagor, Charles R. Manning, and Langley Research Center (page images at HathiTrust)
• Stress-corrosion cracking of Ti-6Al-4V titanium alloy in nitrogen tetroxide / (Washington, D.C. : National Aeronautics and Space Administration ; Springfield, Va. : For sale by the Clearinghouse for Federal Scientific and Technical Information, [1968]), by W. Barry Lisagor, Thomas T. Bales, Charles R. Manning, and Langley Research Center (page images at HathiTrust)
• Coatings and surface treatments for longtime protection of Ti-8Al-1Mo-1V alloy sheet from hot-salt stress corrosion / (Washington, D.C. : National Aeronautics and Space Administration ; Springfield, Va. : For sale by the Clearinghouse for Federal Scientific and Technical Information, [1968]), by Bland A. Stein, Dick M. Royster, H. Benson Dexter, and Langley Research Center (page images at HathiTrust)
• Friction and wear of titanium alloys and copper alloys sliding against titanium - 6-percent-aluminum - 4-percent-vanadium alloy in air at 430C̊ / (Washington : U.S. National Aeronautics and Space Administration ; Springfield, Va. : For sale by the National Technical Information Service, 1976), by Donald W. Wisander, United States National Aeronautics and Space Administration, and Lewis Research Center (page images at HathiTrust)
• Selected fretting-wear-resistant coatings for titanium--6-percent-aluminum--4-percent-vanadium alloy / (Washington : U.S. National Aeronautics and Space Administration ; Springfield, Va. : For sale by the National Technical Information Service, 1976), by Robert C. Bill, United States National Aeronautics and Space Administration, and Lewis Research Center (page images at HathiTrust)
• Some factors affecting the stress-corrosion cracking of Ti-6Al-4V alloy in methanol / (Washington, D.C. : National Aeronautics and Space Administration ; [Springfield, Va. : For sale by the Clearinghouse for Federal Scientific and Technical Information, 1969]), by W. Barry Lisagor, United States National Aeronautics and Space Administration, and Langley Research Center (page images at HathiTrust)
• Hot-salt-stress-corrosion cracking and its effect on tensile and stress-rupture properties of Ti-6Al-4V titanium-alloy sheet / (Washington, D.C. : National Aeronautics and Space Administration ; [Springfield, Va. : For sale by the Clearinghouse for Federal Scientific and Technical Information, 1969]), by Dick M. Royster, United States National Aeronautics and Space Administration, and Langley Research Center (page images at HathiTrust)
• Ti-6A1-4V alloy castings prepared in zircon sand molds and the effect of hot isostatic pressing / ([Pittsburgh, PA] : U.S. Dept. of the Interior, Bureau of Mines, [1984]), by J. I. Paige, Jack L. Henry, and P. G. Clites (page images at HathiTrust)
• Soft body impact damage effects on boron-aluminum composites /, by William J. Jaques and issuing agency Air Force Materials Laboratory (U.S.) (page images at HathiTrust)

• Salt stress corrosion of residually stressed Ti-8Al-1Mo-1V alloy sheet after exposure at elevated temperatures / (Washington, D.C. : National Aeronautics and Space Administration ; Springfield, Va. : For sale by the Clearinghouse for Federal Scientific and Technical Information, [1966]), by Howard B. Dexter and Langley Research Center (page images at HathiTrust)

• The titanium-vanadium system / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Technical Information Service, 1952), by R. M. Powers, H. A. Wilhelm, Ames Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Improvements in consolidation and fabrication of vanadium-20 w/o titanium(TV-20) /, by W. R. Burt, R. M. Mayfield, F. J. Karasek, W. C. Kramer, and Argonne National Laboratory (page images at HathiTrust)

• Corrosion studies of ternary zirconium alloys in high-temperature water and steam / (Argonne, Ill. : Argonne National Laboratory, Metallurgy Division, 1961), by R. D. Misch, C. Van Drunen, and Argonne National Laboratory (page images at HathiTrust)
• Determination of the effect of high excess H₂SO₄ concentrations on the radiation-induced corrosion of zirconium and titanium alloys in 0.17 m UO₂SO₄ / (Oak Ridge, Tenn. : 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)
• The thermal analysis of zirconium - tin alloys / (Schenectady, N.Y. : Knolls Atomic Power Laboratory, 1952), by L. L. Wyman, J. F. Bradley, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Properties of reactor fuel rod materials at high temperatures : final summary report : severe core damage property tests program / (Washington, DC : 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)
• Preliminary analysis of surface displacement results in the creepdown irradiation experiment HOBBIE-1 /, by D. O. Hobson, issuing body Oak Ridge National Laboratory. Metals and Ceramics Division, and sponsor U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research (page images at HathiTrust)
• Plutonium-238 isotopic fuel form data sheets /, 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)
• Evaluating strength and ductility of irradiated zircaloy, task 5 / (Washington, D.C. : The Commission, 1981-), 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 : quarterly progress report January-March, 1979 / (Washington, D.C. : 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 July - September 1979 / (Washington, D.C. : 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)
• Ignition behavior and kinetics of oxidation of the reactor metals, uranium, zirconium, plutonium, and thorium, and binary alloys of each : a status report / (Lemont, Ill. : Argonne National Laboratory, 1959), by J. G. Schnizlein, U.S. Atomic Energy Commission. ANL., and Argonne National Laboratory. Chemical Engineering Division. ANL (page images at HathiTrust)
• The effects of irradiation on some binary alloys of thorium-plutonium and zirconium-plutonium / (Argonne, Ill. : Argonne National Laboratory, 1962), by J. A. Horak, H. V. Rhude, J. H. Kittel, U.S. Atomic Energy Comission. ANL, and Argonne National Laboratory. Metallurgy Division. ANL (page images at HathiTrust)
• Studies of the hydrogen damage mechanism in the corrosion of zirconium / (Argonne, Ill. : Argonne National Laboratory, 1961), by R. D. Misch, U.S. Atomic Energy Commission. ANL., and Argonne National Laboratory. Metallurgy Division. ANL (page images at HathiTrust)
• Corrosion properties of the TZM and molybdenum-30 tungsten alloys / ([Washington, D.C.] : 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)
• Investigation of pyrolytic graphite as crucible material for zirconium melting / (Richland, Wash. : Hanford Atomic Products Operation, 1962), by R. E. Westerman, U.S. Atomic Energy Commission. AEC research and develpment report, U.S. Atomic Energy Commission. TID., U.S. Atomic Energy Commission, Hanford Atomic Products Operation Reactor and Fuels Research and Development Operation, and Pacific Northwest Laboratory (page images at HathiTrust)
• The zirflex process : terminal development report / (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by P. W. Smith, United States. National Bureau of Standards. UC., United States. Department of Energy. Office of Fusion Energy. UC., United States. National Bureau of Standards. Fracture and Deformation Division. UC., U.S. Atomic Energy Commission. AEC research and development report, Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust)
• Hydriding in purposely defected, zircaloy-clad fuel rods / (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by M. K. Millhollen, J. Lambert Bates, G. R. Horn, United States. National Bureau of Standards. UC., United States. Department of Energy. Office of Fusion Energy. UC., United States. National Bureau of Standards. Fracture and Deformation Division. UC., U.S. Atomic Energy Commission. AEC research and development report, United States. Energy Research and Development Administration. TID., U.S. Atomic Energy Commission. TID., 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. (Richland, Wash. : Hanford Atomic Products Operation, 1961), by Spencer Harrison Bush, D. L. Gray, R. S. Kemper, United States. National Bureau of Standards. UC., United States. Department of Energy. Office of Fusion Energy. UC., United States. National Bureau of Standards. Fracture and Deformation Division. UC., U.S. Atomic Energy Commission. AEC research and development report, United States. Energy Research and Development Administration. TID., U.S. Atomic Energy Commission. TID., 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 / (Richland, Wash. : Hanford Atomic Products Operation, 1961), by H. C. Bowen, United States. National Bureau of Standards. UC., United States. Department of Energy. Office of Fusion Energy. UC., United States. National Bureau of Standards. Fracture and Deformation Division. UC., U.S. Atomic Energy Commission. AEC research and development report, United States. Energy Research and Development Administration. TID., U.S. Atomic Energy Commission. TID., Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust)
• Some effects of cold rolling, annealing and aging on the mechanical properties of Zircaloy-3b / (Richland, Wash. : U.S. Atomic Energy Commission, 1957), by D. E. Johnson, United States. National Bureau of Standards. UC., United States. Department of Energy. Office of Fusion Energy. UC., United States. National Bureau of Standards. Fracture and Deformation Division. UC., U.S. Atomic Energy Commission. AEC research and development report, United States. Energy Research and Development Administration. TID., U.S. Atomic Energy Commission. TID., Hanford Works, and Hanford Atomic Products Operation. Research and Development Research and Development Operation (page images at HathiTrust)
• Phase diagram studies of zirconium with silver, indium, and antimony / (Oak Ridge, Tenn. : 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)
• Summary report : an evaluation of the substitution of zircaloy for stainless steel in N.S. Savannah fuel-element containers / (Oak Ridge, Tenn. : 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)
• Salt-phase chlorination of reactor fuels. (Idaho Falls, Idaho : 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 / (Idaho Falls, Idaho : 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. ([Idaho Falls, Idaho] : 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)
• Anodic oxidation of zirconium at low potentials : effect of electrolyte composition / (Oak Ridge, Tenn. : 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)
• Development of zirconium alloys. (Oak Ridge, Tenn. : 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)
• Zirconium alloys for nuclear reactor applications / (Oak Ridge, Tenn. : 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)
• Tensile-creep properties at 500 F of zirconium and a 3.66 per cent uranium alloy of zirconium / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Technical Information Service, [1955]), by A. D. Schwope, G. T. Muehlenkamp, Battelle Memorial Institute, and U.S. Atomic Energy Commission. Technical Information Service (page images at HathiTrust)
• Mechanical properties of ternary zirconium alloys / (Oak Ridge, Tenn. : United States Atomic Energy Commission, Technical Information Service, [1955]), by A. D. Schwope, Walston Chubb, Battelle Memorial Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Kinetics of the zirconium-nitrogen and zirconium-tin-nitrogen systems / (Oak Ridge, Tenn. : 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 / (Oak Ridge, Tenn. : 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)
• Corrosion of uranium-zirconium alloys in water at temperatures up to 100 C / (Oak Ridge, Tenn. : 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)
• Effect of radiation on the thermal conductivity of uranium-1.6 w/o zirconium / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Technical Information Service Extension, [1957]), by G. D. Calkins, C. F. Lucks, E. C. Lusk, H. W. Pobereskin, H. W. Deem, 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 / (Columbus, OH : 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)
• Development of high-strength corrosion-resistant zirconium alloys / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from the Office of Technical Services, U.S. Dept. of Commerce, [1960]), by John A. DeMastry, Ronald F. Dickerson, Frederic R. Shober, 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 / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from Office of Technical Services, U.S. Dept. of Commerce, [1962]), by Warren E. Berry, Frederick W. Fink, Earl L. White, 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 / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from Office of Technical Services, U.S. Dept. of Commerce, [1962]), by Ronald J. Carlson, Stanley W. Porembka, Stan J. Paprocki, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Recovery of uranium from zirconium-uranium alloy / (Aiken, South Carolina : 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 / (Aiken, South Carolina : 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 / (Aiken, S.C. : 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 / (Aiken, S.C. : 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)
• Thermal-stress-fatigue behavior of zirconium and zirconium alloys : final report / (Oak Ridge, Tennessee : 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)
• Effect of welding atmosphere and pickling on the corrosion resistance of welded zircaloy-2 and -3 / (Schenectady, N.Y. : 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)
• Investigations of binary zirconium alloys / (Schenectady, N.Y. : 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 /, by D. S. Kneppel, T. T. Magel, Massachusetts Institute of Technology, and U.S. Atomic Energy Commission (page images at HathiTrust)
• A preliminary study of high-strength zirconium-base alloys /, by S. R. Maloof, U.S. Atomic Energy Commission, and Inc Nuclear Metals (page images at HathiTrust)
• The powder metallurgy of zirconium-tin alloys., by Henry H. Hausner, Richard M. Treco, Inc Sylvania Electric Products, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Thermal expansion of zirconium and zirconium-tin alloys up to 570°C /, by Marvin Moskowitz, L. W. Kates, 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 /, by Fred D. Rosi, F. C. Perkins, Inc Sylvania Electric Products, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Hydrogen redistribution in thin plates of zirconium under large thermal gradients /, by J. M. Markowitz, 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 /, 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)
• High-temperature water and steam-corrosion behavior of zirconium-uranium alloys /, by Stanley Kass, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• The thermal analysis of zirconium-tin alloys /, by L. L. Wyman, J. F. Bradley, Knolls Atomic Power Laboratory, U.S. Atomic Energy Commission, and General Electric Company (page images at HathiTrust)
• Evaluating strength and ductility of irradiated zircaloy, task 5 : quarterly progress report, April-June 1978 / (Washington, D.C. : 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 / (Washington, D.C. : 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 April - June, 1979 / (Washington, D.C. : 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 / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, 1953), by R. D. Misch, U.S. Atomic Energy Commission. ANL., and Argonne National Laboratory. ANL. (page images at HathiTrust)
• Electrical measurements on the growing scale on zirconium-titanium alloys / (Argonne, Ill. : Argonne National Laboratory, 1961), by R. D. Misch, G. W. Iseler, U.S. Atomic Energy Comission. ANL, and Argonne National Laboratory. Metallurgy Division. ANL (page images at HathiTrust; US access only)
• High-temperature enthalpy and x-ray powder diffraction data for ZrI4 / ([Washington, D.C.] : U.S. Dept. of the Interior, Bureau of Mines, 1980), by M. J. Ferrante and R. A. McCune (page images at HathiTrust)
• A preliminary survey of zirconium alloys / ([Washington, D.C.] : 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)
• Determination of a part of the magnesium-zirconium liquidus / ([Washington, D.C.] : 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 / ([Washington, D.C.] : 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 / ([Washington, D.C.] : U.S. Dept. of the Interior, Bureau of Mines, 1961), by Mark I. Copeland, H. Kato, and Clo E. Armantrout (page images at HathiTrust)
• Effects of aluminum, nitrogen, manganese, and copper impurities on hot water and steam corrosion rates of zircaloy-3 / ([Washington, D.C.] : 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)
• Effect of impurity levels on zircaloy 2 microstructure, mechanical properties, and corrosion rates / ([Washington, D.C.] : 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, Tenn., 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 / (Richland, Wash. : Hanford Atomic Products Operation, 1961), by J. J. Holmes, U.S. Atomic Energy Commission. AEC research and develpment report, U.S. Atomic Energy Commission. TID., U.S. Atomic Energy Commission, Hanford Atomic Products Operation, and Pacific Northwest Laboratory (page images at HathiTrust)
• Role of the oxidation rate on the hydriding of zirconium alloys in gas atmospheres containing hydrogen / (Richland, Wash. : U.S. Atomic Energy Commission, 1963), by D. W. Shannon, United States. National Bureau of Standards. UC., United States. Department of Energy. Office of Fusion Energy. UC., United States. National Bureau of Standards. Fracture and Deformation Division. UC., U.S. Atomic Energy Commission. AEC research and development report, United States. Energy Research and Development Administration. TID., U.S. Atomic Energy Commission. TID., Hanford Works, and Hanford Atomic Products Operation. Reactor and Fuels 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 / (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by P. L. Farnsworth, K. M. Haws, United States. National Bureau of Standards. UC., United States. Department of Energy. Office of Fusion Energy. UC., United States. National Bureau of Standards. Fracture and Deformation Division. UC., U.S. Atomic Energy Commission. AEC research and development report, United States. Energy Research and Development Administration. TID., U.S. Atomic Energy Commission. TID., 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 / (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by S. H. Bush, United States. National Bureau of Standards. UC., United States. Department of Energy. Office of Fusion Energy. UC., United States. National Bureau of Standards. Fracture and Deformation Division. UC., U.S. Atomic Energy Commission. AEC research and development report, United States. Energy Research and Development Administration. TID., U.S. Atomic Energy Commission. TID., 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 / (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by L. E. Mills, United States. National Bureau of Standards. UC., United States. Department of Energy. Office of Fusion Energy. UC., United States. National Bureau of Standards. Fracture and Deformation Division. UC., U.S. Atomic Energy Commission. AEC research and development report, United States. Energy Research and Development Administration. TID., U.S. Atomic Energy Commission. TID., Hanford Works, and Hanford Atomic Products Operation. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
• Autoclave testing of zircaloy-2 / (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by R. A. Thiede, United States. National Bureau of Standards. UC., United States. Department of Energy. Office of Fusion Energy. UC., United States. National Bureau of Standards. Fracture and Deformation Division. UC., U.S. Atomic Energy Commission. AEC research and development report, United States. Energy Research and Development Administration. TID., U.S. Atomic Energy Commission. TID., 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. (Richland, Wash. : Hanford Atomic Products Operation, 1961), by D. L. Gray, United States. National Bureau of Standards. UC., United States. Department of Energy. Office of Fusion Energy. UC., United States. National Bureau of Standards. Fracture and Deformation Division. UC., U.S. Atomic Energy Commission. AEC research and development report, United States. Energy Research and Development Administration. TID., U.S. Atomic Energy Commission. TID., 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. (Richland, Wash. : Hanford Atomic Products Operation, 1961), by S. H. Bush, D. L. Gray, R. S. Kemper, United States. National Bureau of Standards. UC., United States. Department of Energy. Office of Fusion Energy. UC., United States. National Bureau of Standards. Fracture and Deformation Division. UC., U.S. Atomic Energy Commission. AEC research and development report, United States. Energy Research and Development Administration. TID., U.S. Atomic Energy Commission. TID., 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. (Richland, Wash. : Hanford Atomic Products Operation, 1961), by Spencer Harrison Bush, R. S. Kemper, United States. National Bureau of Standards. UC., United States. Department of Energy. Office of Fusion Energy. UC., United States. National Bureau of Standards. Fracture and Deformation Division. UC., U.S. Atomic Energy Commission. AEC research and development report, United States. Energy Research and Development Administration. TID., U.S. Atomic Energy Commission. TID., 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 / (Richland, Wash. : Hanford Atomic Products Operation, 1961), by R. L. Knecht, United States. National Bureau of Standards. UC., United States. Department of Energy. Office of Fusion Energy. UC., United States. National Bureau of Standards. Fracture and Deformation Division. UC., U.S. Atomic Energy Commission. AEC research and development report, United States. Energy Research and Development Administration. TID., U.S. Atomic Energy Commission. TID., Hanford Works, and Hanford Atomic Products Operation. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
• Multiple rate transitions in the aqueous corrosion of zircaloy / (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by B. Griggs, D. W. Shannon, H. P. Maffei, United States. National Bureau of Standards. UC., United States. Department of Energy. Office of Fusion Energy. UC., United States. National Bureau of Standards. Fracture and Deformation Division. UC., U.S. Atomic Energy Commission. AEC research and development report, United States. Energy Research and Development Administration. TID., U.S. Atomic Energy Commission. TID., Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust)
• Mechanisms and kinetics of uranium corrosion and uranium core fuel element ruptures in water and steam / (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by V. H. Troutner, United States. National Bureau of Standards. UC., United States. Department of Energy. Office of Fusion Energy. UC., United States. National Bureau of Standards. Fracture and Deformation Division. UC., U.S. Atomic Energy Commission. AEC research and development report, United States. Energy Research and Development Administration. TID., U.S. Atomic Energy Commission. TID., Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust)
• Temperature distributions of reactor fuel element end caps / (Richland, Wash. : U.S. Atomic Energy Commission, 1961), by K. R. Merckx, United States. National Bureau of Standards. UC., United States. Department of Energy. Office of Fusion Energy. UC., United States. National Bureau of Standards. Fracture and Deformation Division. UC., U.S. Atomic Energy Commission. AEC research and development report, United States. Energy Research and Development Administration. TID., U.S. Atomic Energy Commission. TID., Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust)
• Extrusion characteristics of uranium-zirconium and uranium-carbon alloys / (Richland, Wash. : U.S. Atomic Energy Commission, 1961), by J. C. Tverberg, J. J. Holmes, United States. National Bureau of Standards. UC., United States. Department of Energy. Office of Fusion Energy. UC., United States. National Bureau of Standards. Fracture and Deformation Division. UC., U.S. Atomic Energy Commission. AEC research and development report, United States. Energy Research and Development Administration. TID., U.S. Atomic Energy Commission. TID., Hanford Works, and Hanford Atomic Products Operation. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
• The effect of reactor atmosphere on zirconium and zirconium alloys / (Richland, Wash. : U.S. Atomic Energy Commission, 1958), by R. G. Wheeler, United States. National Bureau of Standards. UC., United States. Department of Energy. Office of Fusion Energy. UC., United States. National Bureau of Standards. Fracture and Deformation Division. UC., U.S. Atomic Energy Commission. AEC research and development report, United States. Energy Research and Development Administration. TID., U.S. Atomic Energy Commission. TID., Hanford Works, and Hanford Atomic Products Operation. Fuels Development Operation (page images at HathiTrust)
• A study of the short time annealing of cold worked zirconium / (Richland, Wash. : Hanford Atomic Products Operation, 1956), by D. E. Johnson, U.S. Atomic Energy Commission. AEC research and develpment report, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
• A calorimetric investigation of zirconium, titanium, and zirconium alloys from 60 to 960⁰ C / (Oak Ridge, Tenn. : 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, Tenn. : 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)
• The solubility of zirconium tetrafluoride in nitric acid from 0 to 80©� C / ([Idaho Falls, Idaho] : Idaho Operations Office, U.S. Atomic Energy Commission, 1958), by A. G. Chapman, C. M. Slansky, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
• Preliminary x-ray investigations of the hydrates of zirconium tetrafluoride / ([Idaho Falls, Idaho] : 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)
• Salt-phase chlorination of reactor fuels. ([Idaho Falls, Idaho] : 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)
• An improved aqueous process for zirconium alloy nuclear reactor fuels. ([Idaho Falls, Idaho] : 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 / (Oak Ridge, Tenn. : 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 / (Oak Ridge, Tenn. : 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)
• Tensile properties of zirconium and zirconium alloys. (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Technical Information Service, 1955.), by C. R. Simcoe, W. L. Mudge, Westinghouse Electric Corporation. Atomic Power Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• The anodic oxidation of some dilute binary zirconium alloys / (Oak Ridge, Tenn. : 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 / (Oak Ridge, Tenn., 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)
• An evaluation of materials of construction for the Sulflex [sic] and Zirflex processes / (Upton, N.Y. : 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 / (Oak Ridge, Tenn. : 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. (Oak Ridge, Tenn. : 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)
• A hot-hardness survey of the zirconium-uranium system / (Oak Ridge, Tenn. : United States Atomic Energy Commission, Technical Information Service, [1955]), by Walston Chubb, A. D. Schwope, G. T. Muehlenkamp, Battelle Memorial Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Creep of zirconium-tin alloys / (Oak Ridge, Tenn. : United States Atomic Energy Commission, Technical Information Service, [1955]), by Walston Chubb, A. D. Schwope, Battelle Memorial Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Effect of hydrogen on mechanical properties of zirconium and its tin alloys / (Oak Ridge, Tenn. : United States Atomic Energy Commission, 1953), by G. T. Muehlenkamp, A. D. Schwope, Battelle Memorial Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Induction-melted zirconium and zirconium alloys / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Technical Information Service, [1955]), by Henry A. Saller, E. L. Foster, Robert F. Dickerson, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• A high strength zirconium alloy : zirconium - 4 w/o tin - 1.6 w/o molybdenum / (Oak Ridge, Tenn. : 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 / (Oak Ridge, Tenn. : 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 heat treatment, transformation reactions, and mechanical properties of some high-strength zirconium-base alloys / (Columbus, OH : Battelle Memorial Institute, [1956]), by P. D. Frost, Morris W. Mote, J. Robert Doig, Herbert A. Robinson, 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 / (Columbus, OH : Battelle Memorial Institute, [1957]), by Alexis W. Lemmon, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Progress relating to civilian applications during ... (Columbus, OH : Battelle Memorial Institute.), by Battelle Memorial Institute and U.S. Atomic Energy Commission. Technical Information Service Extension (page images at HathiTrust)
• The effect of primary alpha on the beta decomposition of zirconium-uranium-oxygen alloys / (Columbus, OH : Battelle Memorial Institute, [1958]), by D. L. Douglass, Lyle L. Marsh, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• An evaluation of the properties and behavior of zirconium-uranium alloys / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from Office of Technical Services, U.S. Dept. of Commerce, [1959]), by Arthur A. Bauer, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Hydrogen pickup during corrosion of zirconium alloys / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from the Office of Technical Services, U.S. Dept. of Commerce, [1959]), by Warren E. Berry, Earl L. White, D. A. Vaughan, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• High temperature irradiation of a zirconium-hydride-2 w/o uranium alloy / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from the Office of Technical Services, U.S. Dept. of Commerce, [1959]), by Ronald F. Dickerson, Euguen M. Simons, John H. Stang, Alan K. Hopkins, H. H. Krause, Alan W. Hare, Gerald E. Lamale, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Investigation of the yield phenomenon in Zircaloy-2 at elevated temperatures / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from Office of Technical Services, U.S. Dept. of Commerce, 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 / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from Office of Technical Services, U.S. Dept. of Commerce, 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 / (Columbus, OH : 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 (U₀₃Zr₀₇)C in the temperature range 1400©�K to 2800©�K / (Los Alamos, N.M. : 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, Iowa] : 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 / (Columbus, OH : Battelle Memorial Institute, [1956]), by Karl A. Sense, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Tensile properties of sheet zirconium at room and elevated temperatures / (Columbus, Ohio : Battelle Memorial Institute, [1950]), by A. D. Schwope, G. T. Muehlenkamp, S. J. Stockett, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Irradiation of tandem-extruded joints between zircaloy and stainless steel / (Aiken, South Carolina : E.I. du Pont de Nemours & Company, Savannah River Laboratory, 1963), by J. Walter Joseph, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Dissolution of zirconium alloy fuels in 309SCb stainless steel vessels / (Aiken, South Carolina : E.I. du Pont de Nemours & Company, Savannah River Laboratory, 1964), by Edward S. Occhipinti, V. P. Caracciolo, J. Harding Owen, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Mechanical properties of irradiated zirconium, zircaloy, and aluminum : a summary of the data in the literature / (Aiken, S.C. : E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, [1961]), by Richard E. Schreiber, Erminia U. Kauer, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Specific zirconium alloy design program quarterly progress report. (San Jose, Calif. : General Electric, Nuclear Fuels Dept.), by Joint U.S.-Euratom Research and Development Program, U.S. Atomic Energy Commission, and General Electric Company. Nuclear Fuels Department (page images at HathiTrust)
• Corrosion mechanism of zirconium and its alloys : diffusion of oxygen in zirconium dioxide / (Oak Ridge, Tenn. : 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)
• Proceedings of the USAEC symposium on zirconium alloy development, Castlewood, Pleasanton, California, November 12-14, 1962 / (San Jose, Calif. : 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)
• Hydrogen overvoltage and electrochemical potentials of zirconium and zirconium intermetallics / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Division of Technical Information, 1963), by J. S. Armijo, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Design and fabrication of fuel rods clad with stainless-steel-lined zircaloy-2 / (Oak Ridge, Tenn. : 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)
• Properties of hydrided zirconium / (Cincinnati, Ohio : General Electric, Aircraft Nuclear Propulsion Dept., 1959), by D. S. Parker, C. L. Huffine, General Electric Company. Aircraft Nuclear Propulsion Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Metallographic study of the system ZrHx / (Cincinnati, Ohio : General Electric, Nuclear Materials and Propulsion Operation, 1961), by Donald Whitwham, R. VanHouten, General Electric Company. Nuclear Materials and Propulsion Operation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Chemical base coatings for zirconium and zircaloy / (Oak Ridge, Tennessee : 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)
• Production of molybdenum-uranium and zirconium-uranium alloys / (Paducah, KY : 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)
• Fundamental and applied research and development in metallurgy : development of zirconium-base alloys strengthened by SLIS techniques : summary technical report to the United States Atomic Energy Commission for the period July 1, 1963 through June 30, 1964 /, by A. R. Kaufmann, W. C. Muller, U.S. Atomic Energy Commission, and Inc Nuclear Metals (page images at HathiTrust)
• Prediction of high temperature tensile and creep properties from hot hardness tests of a Zr-Nb-Sn alloy / (Schenectady, N.Y. : Knolls Atomic Power Laboratory, General Electric Company, 1959), by D. L. Douglass, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• Theoretical kinetics and stresses for delta-phase isothermal hydriding of uranium-zirconium / (Canoga Park, California : 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 / (Canoga Park, California : Atomics International, [1961]), by R. K. Wagner, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Oxidation of zirconium and zirconium alloys in liquid sodium / (Canoga Park, California : Atomics International, [1962]), by T. L. Mackay, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• A method for differentiating between materials containing normal and fully enriched uranium /, by R. C. Barry, A. R. Mooers, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• High-strength zirconium alloys / (Canoga Park, California : 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)
• Rapid pulse heating of modified zirconium-uranium hydrides to destruction : (final report) / (Canoga Park, California : Atomics International, [1965]), by R. A. Finch, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Effect of heat treatment on the corrosion behavior of zirconium binary alloys of nickel and iron /, by D. S. Kneppel, Inc Nuclear Metals, and U.S. Atomic Energy Commission (page images at HathiTrust)
• The chemical analysis of zirconium and zircaloy metals /, by E. B. Read, H.M. Read, Inc Nuclear Metals, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Corrosion of zirconium alloys in 900° steam /, by J. Paul Pemsler, 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 /, 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)
• The physical properties of sintered zirconium /, by Herbert S. Kalish, Roswell P. Angier, Henry H. Hausner, Inc Sylvania Electric Products, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Dilatometric studies of zirconium and zirconium-tin alloys between 25° and 1100°C /, by R. W. Balluffi, A. J. Timper, R. Resnick, 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 /, by John J. Kearns, Westinghouse Electric Corporation, Bettis Atomic Power Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Zirconium, zircaloy, and hafnium safe practice guide for shipping, storing, handling, processing, and scrap disposal /, by W. W. Allison, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Corrosion testing of Zircaloy-2 and Zircaloy-3 /, by Stanley Kass, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• The corrosion of zircaloy base fuel alloys in high temperature water /, by Stanley Kass, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Interim report of creep behavior of Zircaloy-2 and -3 /, by W. D. McMullen, 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 /, 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)
• The evolution of xenon-133 from slightly irradiated zirconia-urania plates /, by J. C. Clayton, Bettis Atomic Power Laboratory, Westinghouse Electric Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Preliminary investigation concerning the formation of zirconium-magnesium alloys by powder metallurgical methods /, by Henry H. Hausner, Herbert S. Kalish, Inc Sylvania Electric Products, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Yankee Core Evaluation Program, quarterly progress report for the period ending ... (Pittsburgh, Pa. : Westinghouse Electric Corporation, Atomic Power Division.), by U.S. Atomic Energy Commission. New York Operations Office and Westinghouse Electric Corporation. Atomic Power Division (page images at HathiTrust)
• Evaluating strength and ductility of irradiated zircaloy task 5 : quarterly progress report April - June, 1978 /, 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)
• A report on some attempts to cast centrifugally fuel elements of small diameter / (Argonne, Ill. : Argonne National Laboratory, Metallurgy Division, 1961), by F. L. Yaggee, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
• Magnesium-zirconium diffusion studies / (Schenectady, N.Y. : Knolls Atomic Power Laboratory, General Electric Company, 1957), by L. S. DeLuca, D. D. Van Horn, H. T. Sumsion, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust; US access only)
• Explosions occurring during chemical etching or pickling of uranium-zirconium alloys /, by H. P. Roth, Massachusetts Institute of Technology, and U.S. Atomic Energy Commission (page images at HathiTrust)
• High strength zirconium-base alloys /, by G. A. Henrikson, Inc Nuclear Metals, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Vapor pressures of the sodium fluoride-zirconium fluoride system and derived information /, 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 cold working of extruded zircaloy tubing /, by N. R. Gardner, P. Loewenstein, Inc Nuclear Metals, 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 /, 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 January-March, 1978 / (Washington, D.C. : The Commission ; Springfield, Virginia. : Available from National Technical Information Service, 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)
• The effect of transients and longer time anneals on irradiated uranium-zirconium alloys / (Schenectady, N.Y. : Knolls Atomic Power Laboratory, General Electric Company, 1958), by William V. Johnston, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust; US access only)
• Preparation of nuclear poison and control alloys : zirconium base - boron alloys / (Schenectady, N.Y. : 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)
• Corrosion of zirconium alloys in 900 and 1000° steam /, by J. Paul Pemsler, Inc Nuclear Metals, and U.S. Atomic Energy Commission (page images at HathiTrust)
• The determination of uranium in zirconium-uranium alloys /, by Clara Gale Goldbeck, Theresa DeGroot, Zaida Martinez, sponsor U.S. Atomic Energy Commission. New York Operations Office, and sponsor New Brunswick Laboratory (page images at HathiTrust)

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