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Zircaloy-2

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• Zirconium alloys

• Fabrication of the PRTR zircaloy-2 high pressure process tubes / (Richland, Wash. : Hanford Atomic Products Operation, 1959), by R. L. Knecht, General Electric Company, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
• Evaluation of properties of irradiated Zircaloy-2 pressure tube from KER Loop 1 / (Richland, Wash. : Hanford Atomic Products Operation, 1962), by L. J. Defferding, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
• Strength and metallurgical properties of the Zircaloy-2 pressure tubes for the PRTR / (Richland, Wash. : Hanford Atomic Products Operation, 1962), by R. L. Knecht, P. J. Pankaskie, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
• Corrosion of zircaloy in crevices under nucleate boiling conditions / (Schenectady, N.Y. : 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)
• Mechanical properties of zircaloy-2 / (Schenectady, N.Y. : Knolls Atomic Power Laboratory, General Electric Company, [1961]), by R. L. Mehan, F. W. Wiesinger, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• Mechanical properties of zircaloy-2 weld metal / (Schenectady, N.Y. : Knolls Atomic Power Laboratory, General Electric Company, [1961]), by S. Beitscher, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• In-pile loop investigations of corrosion of Zircaloy-2 and other possible reactor materials in 0.04 m UO₂SO₄ at 280°C / (Oak Ridge, Tenn. : Oak Ridge National Laboratory, [1960]), by G. H. Jenks, J. E. Baker, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• In-reactor monitoring of zircaloy-2 PRTR pressure tubes. (Richland, Wash. : Hanford Atomic Products Operation, 1962), by D. R. Doman, P. J. Pankaskie, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
• Thin wall tubing tests using ultrasonic shear waves. (Richland, Wash. : Hanford Atomic Products Operation, 1964), by M. F. Zeutschel, N. E. Dixon, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
• In-reactor monitoring of zircaloy-2 PRTR pressure tubes. (Richland, Wash. : Hanford Atomic Products Operation, 1963), by P. J. Pankaskie, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
• An assessment of the long-term storage of zircaloy fuel rods in water : final report / ([Sacramento] : California Energy Commission, [1977]), by Zuhair A Munir and California Energy Commission (page images at HathiTrust)
• An assessment of hydrogen generation for the PBF severe fuel damage scoping and 1-1 test / (Washington, D.C. : Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), by August W. Cronenberg, Daniel J. Osetek, Richard W. Miller, Idaho National Engineering Laboratory, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation, and EG & G Idaho (page images at HathiTrust)
• Inert tungsten-arc welding of S3G zircaloy channel sections /, by S. A. Toftegaard, Knolls Atomic Power Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Creep properties of zircaloy-2 for design application / (Richland, Wash. : Hanford Atomic Products Operation, 1962), by P. J. Pankaskie, U.S. Atomic Energy Commission. AEC research and development report, U.S. Atomic Energy Commission. TID., U.S. Atomic Energy Commission, Hanford Atomic Products Operation, and Pacific Northwest Laboratory (page images at HathiTrust)
• In-reactor monitoring of zircaloy-2 PRTR pressure tubes. (Richland, Wash. : Hanford Atomic Products Operation, 1962), by D. R. Doman, P. J. Pankaskie, U.S. Atomic Energy Commission. AEC research and development 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)
• Postirradiation evaluation of zircaloy-2 pressure tube from KER-3, preliminary report / (Richland, Wash. : Hanford Atomic Products Operation, 1962), by R. C. Aungst, U.S. Atomic Energy Commission. AEC research and development report, U.S. Atomic Energy Commission. TID., U.S. Atomic Energy Commission, Hanford Atomic Products Operation, and Pacific Northwest Laboratory (page images at HathiTrust)
• Corrosion tests on KER-1 zircaloy-2 process tube / (Richland, Wash. : Hanford Atomic Products Operation, 1961), by H. P. Maffei, 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)
• Effect of low hydrogen concentrations on hall effect in zircaloy-2 / (Richland, Wash. : Hanford Atomic Products Operation, 1961), by W. G. Jr Magnuson, 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)
• Ultrasonic inspection of PRTR fuel element cladding / (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by P. L. Farnsworth, T. G. Lambert, 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)
• The physical integrity and corrosion resistance of the zircaloy-2 pressure tubes for the PRTR / (Richland, Wash. : U.S. Atomic Energy Commission, 1960), 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 (page images at HathiTrust)
• High frequency resistance welding of spacer ribs to zircaloy-2-clad UO₂ fuel components / (Richland, Wash. : U.S. Atomic Energy Commission, 1961), by L. R. Vancott, 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)
• Neutron irradiation effects on the tensile properties of Zircaloy-2 / (Richland, Wash. : U.S. Atomic Energy Commission, 1957), by R. S. Kemper, D. L. Zimmerman, 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)
• Interim report on creep characteristics of Zircaloy-2 / (Richland, Wash. : U.S. Atomic Energy Commission, 1959), by P. J. Pankaskie, 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)
• Electrolytic disintegration of zircaloy-2 in nitric acid solutions / (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1959), by Walter E. Clark, Sigfred Peterson, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Chemical Technology Division. Chemical Development Section A. (page images at HathiTrust)
• Zirflex process for PWR blanket fuel : (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1960), by L. M. Ferris, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory. Chemical Technology Division (page images at HathiTrust)
• Report on the physical behavior of zircaloy-2 plate material produced by the Park Works of the Crucible Steel Company of America from ingot no. 710D640P72BK / (Oak Ridge, Tenn. : United States Atomic Energy Commission, Technical Information Service, 1954), by L. F. Biedsoe, Newport News Shipbuilding and Dry Dock Company, and Crucible Steel Company of America (page images at HathiTrust)
• Stress relaxation in zircaloy-2 during irradiation at less than 100©�C / (Aiken, S.C. : E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, [1961]), by J. Walter Joseph, 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 / (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)
• Corrosion of the zircaloy-2 - niobium couple / (Schenectady, N.Y. : 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)
• A summary of the work associated with the solution and understanding of stringer-type corrosion in Zircaloy-2 and -3 /, 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)
• Weight-shape conversion tables for Zircaloy-2 /, by J. G. Goodwin, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Hydrogen absorption in zircaloy during aqueous corrosion : effect of environment /, by E. Hillner, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Hydriding of zircaloy-2 : a literature search /, by Myra S. Feldman, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Oxide particle size distribution from shearing irradiated and unirradiated LWR fuels in Zircaloy and stainless steel cladding : significance for risk assessment /, by W. Davis, R. G. Stacy, G. A. West, United States. Department of Energy, Oak Ridge National Laboratory. Chemical Technology Division, and U.S. Nuclear Regulatory Commission. Division of Fuel Cycle and Material Safety (page images at HathiTrust)
• Studies of metal-water reactions at high temperatures. (Argonne, Ill. : Argonne National Laboratory, 1962), by Frank J. Testa, Marshall F. Deerwester, Richard O. Ivins, Robert C. Liimatainen, U.S. Atomic Energy Commission. ANL., and Argonne National Laboratory. Chemical Engineering Division. ANL (page images at HathiTrust)
• Review and correlation of in-pile zircaloy-2 corrosion data and a model for the effect of irradiation / (Oak Ridge, Tenn., Oak Ridge National Laboratory, 1961), by G. H. Jenks and U.S. Atomic Energy Commission (page images at HathiTrust)
• In-pile-autoclave test of zircaloy-2 corrosion in UO₂(NO₃)₂ solution and of solution stability / (Oak Ridge, Tenn., Oak Ridge National Laboratory, 1962), by H. C. Savage, S. E. Bolt, V. A. DeCarlo, E. G. Bohlmann, G. H. Jenks, R. J. Davis, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory. Reactor Chemistry Division (page images at HathiTrust)
• Crack propagation tests on normal and hydrided Zircaloy-2 reactor pressure tubing / (Richland, Wash. : Hanford Atomic Products Operation, 1964), by R. C. Aungst, L. J. Defferding, U.S. Atomic Energy Commission. UC., United States. Energy Research and Development Administration. TID., U.S. Atomic Energy Commission. AEC research and development report, and Hanford Atomic Products Operation (page images at HathiTrust)
• The effects of hot-water thermal treatments on the cold work recovery of Zircaloy-2 / (Richland, Wash. : Hanford Atomic Products Operation, 1964), by A. L. Bement, J. E. Irvin, U.S. Atomic Energy Commission. UC., United States. Energy Research and Development Administration. TID., U.S. Atomic Energy Commission. AEC research and development report, and Hanford Atomic Products Operation (page images at HathiTrust)
• Oxide tenacity on alloys exposed to reactor coolants / (Richland, Wash. : Hanford Atomic Products Operation, 1964), by L. D. Perrigo, U.S. Atomic Energy Commission. UC., United States. Energy Research and Development Administration. TID., and U.S. Atomic Energy Commission. AEC research and development report (page images at HathiTrust)
• High temperature oxidation of zirconium and Zircaloy-2 in oxygen and water vapor / (Richland, Wash. : Hanford Atomic Products Operation, 1962), by R. E. Westerman, Richard E. Westerman, U.S. Atomic Energy Commission. AEC research and development report, U.S. Atomic Energy Commission. TID., U.S. Atomic Energy Commission, Hanford Atomic Products Operation, and Pacific Northwest Laboratory (page images at HathiTrust)
• Quantitative metallography of hydride phase in Zircaloy-2 process tubes / (Richland, Wash. : Hanford Atomic Products Operation, 1963), by L. A. Hartcorn, Richard E. Westerman, U.S. Atomic Energy Commission. AEC research and development report, U.S. Atomic Energy Commission. TID., U.S. Atomic Energy Commission, Hanford Atomic Products Operation, and Pacific Northwest Laboratory (page images at HathiTrust)
• Effects of cold work and neutron irradiation on the tensile properties of zircaloy-2 / (Richland, Wash. : Hanford Atomic Products Operation, 1963), by Arden Lee Jr Bement, U.S. Atomic Energy Commission. AEC research and development report, U.S. Atomic Energy Commission. TID., U.S. Atomic Energy Commission, Hanford Atomic Products Operation, and Pacific Northwest Laboratory (page images at HathiTrust)
• Postirradiation evaluation of zircaloy-2 PRTR pressure tubes. (Richland, Wash. : Hanford Atomic Products Operation, 1962), by L. J. Defferding, U.S. Atomic Energy Commission. AEC research and development 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)
• Development of the cathodic etching of metals at pressures from atmospheric to the gaseous discharge region / (Richland, Wash. : Hanford Atomic Products Operation, 1962), by T. B. Correy, U.S. Atomic Energy Commission. AEC research and development report, U.S. Atomic Energy Commission. TID., U.S. Atomic Energy Commission, Hanford Atomic Products Operation Engineering Operation, and Pacific Northwest Laboratory (page images at HathiTrust)
• Head-welded swageable end cap for UO₂-PuO₂ fuel elements / (Richland, Wash. : Hanford Atomic Products Operation, 1962), by L. C. Lemon, W. T. Ross, U.S. Atomic Energy Commission. AEC research and development report, U.S. Atomic Energy Commission. TID., U.S. Atomic Energy Commission, Hanford Atomic Products Operation Plutonium Metallurgy Operation, and Pacific Northwest Laboratory (page images at HathiTrust)
• Impact testing and slow notch-bend testing of zircaloy-2 / (Richland, Wash. : Hanford Atomic Products Operation, 1962), by R. L. Call, U.S. Atomic Energy Commission. AEC research and development 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 activation energies for creep of zircaloy-2 / (Richland, Wash. : Hanford Atomic Products Operation, 1962), 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 Reactor Fuels Research and Development Operation, and Pacific Northwest Laboratory (page images at HathiTrust)
• Final report : irradiation of Zircaloy-2 clad uranium rods in NaK-filled capsules, GEH 3-31, 32, 57, 58, and 59 / (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by J. W. Weber, 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)
• Out-of-reactor evaluation of components and assemblies : Mark I swaged UO₂ PRTR fuel element / (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by M. K. Millhollen, 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)
• Examination of an irradiated, zircaloy-2, hot water loop tube / (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by A. L. Bement, 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)
• Preferred orientations in extruded zircaloy-2 tubing / (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by J. J. Laidler, 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)
• A study of the wear and galling of autoclaved zircaloy-2 by various materials / (Richland, Wash. : U.S. Atomic Energy Commission, 1961), by J. W. Weber, 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)
• Quality evaluation of zircaloy-2 sheath tubing / (Richland, Wash. : U.S. Atomic Energy Commission, 1959), by P. L. Farnsworth, R. B. Socky, H. P. Oakes, 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)
• Burst testing of irradiated zircaloy tubing / (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by V. E. Kahle, 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-2 pilot plant etching and rinsing facility / (Richland, Wash. : Hanford Atomic Products Operation, 1959), by 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. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
• High temperature, high pressure nozzle-to-tube connections for the 1706 KER facility / (Richland, Wash. : U.S. Atomic Energy Commission, 1957), by D. R. Doman, 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 : interim report / (Richland, Wash. : U.S. Atomic Energy Commission, 1958), 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)
• Interim report on the hydrostatic destructive testing of Zircaloy-2 pressure tubing / (Richland, Wash. : U.S. Atomic Energy Commission, 1959), by V. E. Kahle, 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)
• Hydrogen effects on Zircaloy-2 tensile properties / (Richland, Wash. : U.S. Atomic Energy Commission, 1959), by H. H. Burton, 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, Hanford Atomic Products Operation. Reactor and Fuels Research and Development Operation, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
• End closure for plutonium bearing Zircaloy-2-clad fuel elements / (Richland, Wash. : U.S. Atomic Energy Commission, 1959), by L. C. Lemon, 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)
• A review of the properties of Zircaloy-2 / (Richland, Wash. : U.S. Atomic Energy Commission, 1959), by G. E. Zima, 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 Engineering Operation (page images at HathiTrust)
• Preparing Zircaloy-2 for autoclave testing : the pickling and rinsing process / (Richland, Wash. : U.S. Atomic Energy Commission, 1959), by D. W. Shannon, B. Griggs, 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)
• Notch slow-bend testing of zircaloy-2 / (Richland, Wash. : Hanford Atomic Products Operation, 1956), by R. G. Wheeler, 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)
• Hydrofluoric acid decladding of zirconium-clad power reactor fuel elements / (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1958), by W. E. Clark, A. H. Kibbey, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Chemical Technology Division. Chemical Development Section B. (page images at HathiTrust)
• Nuclear analyses of the N.S. Savannah reactor with Zircaloy or stainless steel as fuel-element containers / (Oak Ridge, Tenn., Oak Ridge National Laboratory, 1962), by E. E. Gross, B. W. Colston, M. L. Winton, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory. Reactor Division (page images at HathiTrust)
• Metallurgy of zircaloy-2 : (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1961), by P. L. Rittenhouse, M. L. Picklesimer, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory Metallurgy Division (page images at HathiTrust)
• Metallurgy of zircaloy-2 : (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1960), by P. L. Rittenhouse, M. L. Picklesimer, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory Metallurgy Division (page images at HathiTrust)
• A study of the reaction of metals and water : interim report / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Technical Information Service, 1955), by H. M. Higgins, Aerojet-General Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Irradiation of zircaloy-2 impact specimens containing hydrogen / (Richland, Wash. : Hanford Atomic Products Operation, 1955), by R. G. Wheeler, W. S. Kelly, General Electric Company, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
• Zirconium concentration measurements in the PRTR primary coolant : interim report, December 8, 1962 - June 30, 1963 / (Richland, Wash. : U.S. Atomic Energy Commission, 1963), by T. F. Demmitt, Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust)
• Laboratory simulations of cladding-steam reactions following loss-of-coolant accidents in water-cooled power reactors / by James C. Hesson... [et al] (Lemont, Ill. : Argonne National Laboratory, Reactor Engineering Division, 1970), by Charles Barnes, Kazuo Nishio, Richard E. Wilson, Richard O. Ivins, James C. Hesson, U.S. Atomic Energy Commission, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust)
• Reaction kinetics of zirconium and zircaloy-2 in dry air at elevated temperatures / (Richland, Wash. : 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)
• The mechanical properties of zirconium and zircaloy 2 / (Columbus, OH : Battelle Memorial Institute, [1957]), by John R. Keeler, Lyle L. Marsh, John Andrew Van Echo, Frederic R. Shober, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• The nitric-hydrofluoric acid pickling of zircaloy-2 / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from the Office of Technical Services, U.S. Dept. of Commerce, [1958]), by Frederick W. Fink, P. D. Miller, Warren E. Berry, E. Burt Friedl, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Electron microscopical examination of bonds in zircaloy-2 / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from the Office of Technical Service, U.S. Dept. of Commerce, [1959]), by Arthur P. Young, Charles M. Schwartz, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• A visual study of the corrosion of defected zircaloy-2-clad fuel specimens by hot water / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from the Office of Technical Services, U.S. Dept. of Commerce, [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 / (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, 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 / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from the Office of Technical Services, U.S. Dept. of Commerce, [1960]), by Edward J. Jablonowski, Frederic R. Shober, 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)
• Embrittlement of multipass welds in zircaloy 2 / (Columbus, OH : Battelle Memorial Institute, [1955]), by John T. Niemann, Raeman P. Sopher, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust; US access only)
• Microprobe study of zircaloy corrosion films / (Aiken, S.C. : 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)
• X-ray diffraction studies on zirconium and zircaloy-2 : a literature search / (Aiken, S.C. : E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, [1961]), by Myra S. Feldman, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Destructive evaluation of irradiated zircaloy sheathing / (Aiken, South Carolina : E.I. du Pont de Nemours & Company, Savannah River Laboratory, 1964), by McIntyre R. Louthan, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (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)
• The application of infrared techniques to the study of the corrosion film on zircaloy / (Schenectady, N.Y. : Knolls Atomic Power Laboratory, General Electric Company, 1959), by Herbert Albert Fisch, F. P. Landis, Charles Arlen Kindness, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• Evaluation of by-product zircaloy-2 chips used for metal powder production / (Schenectady, N.Y. : Knolls Atomic Power Laboratory, General Electric Company, 1959), by R. N. Honeyman, E. O. Porter, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• Effect of combined stress on yield and fracture behavior of zircaloy-2 / (Schenectady, N.Y. : Knolls Atomic Power Laboratory, General Electric Company, 1959), by R. L. Mehan, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• Internal-pressure creep-rupture tests of zircaloy-2 tubing / (Schenectady, N.Y. : Knolls Atomic Power Laboratory, General Electric Company, 1960), by G. J. Sokol, D. T. Groleau, 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 /, by A. L. Geary, Inc Nuclear Metals, and U.S. Atomic Energy Commission (page images at HathiTrust)
• The accommodation coefficients of helium and krypton on zircaloy-2 /, by J. M. Markowitz, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Production annealing of Zircaloy-2 /, by J. G. Goodwin, K. M. Goldman, U.S. Atomic Energy Commission, and Westinghouse Electric Corporation. Atomic Power Division (page images at HathiTrust)
• Effect of hydrogen and hydride morphology on the tensile properties of zircaloy-2 / (Washington, D.C. : Available from the Office of Technical Services, Dept. of Commerce, 1963), by W. J. Babyak, G. J. Salvaggio, W. F. Bourgeois, Westinghouse Electric Corporation, Bettis Atomic Power Laboratory, 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 / (Washington, D.C. : 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)
• Irradiation of UO₂ fuel rods : the X-1-L experiment /, by John D. Eichenberg, F. P. Mrazik, Richard M. Lieberman, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Pressure testing of zircaloy tubing /, by L. F. Cochrun, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• The zircaloy-2 in-pile tube for the NRX Central Thimble /, by Richard M. Lieberman, U.S. Atomic Energy Commission, Westinghouse Electric Corporation, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Hydrogen redistribution in zircaloy-2 under thermal and mechanical stress gradients /, by J. M. Markowitz, Westinghouse Electric Corporation, 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 /, 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 /, by R. S Young, issuing body Vallecitos Atomic Laboratory, issuing body U.S. Atomic Energy Commission, and General Electric Company. Atomic Power Equipment Department. issuing body (page images at HathiTrust)
• Zircaloy-2 and type-304 stainless steel at 2000°F in water-steam for brief times /, by R. H. Leyse, issuing body Vallecitos Atomic Laboratory, issuing body U.S. Atomic Energy Commission, and General Electric Company. Atomic Power Equipment Department. issuing body (page images at HathiTrust)
• Development and properties of coextruded zircaloy-clad uranium fuel elements with integral end seals /, by H. F. Sawyer, Inc Nuclear Metals, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Coextrusion of zircaloy-clad U-2 w/o Zr rod for the EBR-I Mark III core loading /, by H. F. Sawyer, Inc Nuclear Metals, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Diffusion annealing as a means of improving corrosion resistance of zircaloy-2 clad, uranium-2 w/o zirconium rods /, by R. G. Jenkins, Inc Nuclear Metals, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Texture of extruded zirconium and zircaloy-2 tubing /, by V. Nerses, Inc Nuclear Metals, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Development of zircaloy-clad, discrete burnable poison elements for S3G/S4G / (Schenectady, N.Y. : Knolls Atomic Power Laboratory, General Electric Company, 1957), by G. F. McKittrick, W. A. Neisz, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust; US access only)
• Effect of hydrogen on the strain fatigue properties of zircaloy-2 weld metal / (Schenectady, N.Y. : Knolls Atomic Power Laboratory, General Electric Company, 1962), by S. Beitscher, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• Review of zircaloy-2 and zircaloy-4 properties relevant to N.S. Savannah reactor design / (Oak Ridge, Tenn., Oak Ridge National Laboratory, 1962), by C. L. Whitmarsh, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory. Reactor Division (page images at HathiTrust)

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