Zircaloy-2 -- MetallurgySee also what's at your library, or elsewhere.
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Filed under: Zircaloy-2 -- Metallurgy High temperature oxidation of zirconium and Zircaloy-2 in oxygen and water vapor (Hanford Atomic Products Operation, 1962), by R. E. Westerman, Richard E. Westerman, U.S. Atomic Energy Commission, Hanford Atomic Products Operation, and Pacific Northwest Laboratory (page images at HathiTrust) Creep properties of zircaloy-2 for design application (Hanford Atomic Products Operation, 1962), by P. J. Pankaskie, 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 (Hanford Atomic Products Operation, 1963), by L. A. Hartcorn, Richard E. Westerman, 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 (Hanford Atomic Products Operation, 1963), by Arden Lee Jr Bement, 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. Part I (Hanford Atomic Products Operation, 1962), by L. J. Defferding, U.S. Atomic Energy Commission, Hanford Atomic Products Operation Reactor and Fuels Research and Development Operation, and Pacific Northwest Laboratory (page images at HathiTrust) In-reactor monitoring of zircaloy-2 PRTR pressure tubes. Part I, September, 1960--May, 1962 (Hanford Atomic Products Operation, 1962), by D. R. Doman, P. J. Pankaskie, 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 (Hanford Atomic Products Operation, 1962), by T. B. Correy, U.S. Atomic Energy Commission, Hanford Atomic Products Operation Engineering Operation, and Pacific Northwest Laboratory (page images at HathiTrust) Impact testing and slow notch-bend testing of zircaloy-2 (Hanford Atomic Products Operation, 1962), by R. L. Call, 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 (Hanford Atomic Products Operation, 1962), by R. C. Aungst, U.S. Atomic Energy Commission, Hanford Atomic Products Operation, and Pacific Northwest Laboratory (page images at HathiTrust) The activation energies for creep of zircaloy-2 (Hanford Atomic Products Operation, 1962), by J. J. Holmes, U.S. Atomic Energy Commission, Hanford Atomic Products Operation Reactor Fuels Research and Development Operation, and Pacific Northwest Laboratory (page images at HathiTrust) Notch slow-bend testing of zircaloy-2 (Hanford Atomic Products Operation, 1956), by R. G. Wheeler, U.S. Atomic Energy Commission, Hanford Atomic Products Operation, and Pacific Northwest Laboratory (page images at HathiTrust) Metallurgy of zircaloy-2 : Part II The effects of fabrication variables on the preferred orientation and anisotropy of strain behavior (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 : Part I The effects of fabrication variables on the anisotropy of mechanical properties (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) Strength and metallurgical properties of the Zircaloy-2 pressure tubes for the PRTR (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) In-reactor monitoring of zircaloy-2 PRTR pressure tubes. Part II, May and June, 1962 (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) In-reactor monitoring of zircaloy-2 PRTR pressure tubes. Part III, July 1963 - November 1963 (Hanford Atomic Products Operation, 1963), by P. J. Pankaskie, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
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Filed under: Zircaloy-2 An assessment of hydrogen generation for the PBF severe fuel damage scoping and 1-1 test (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) TREAT experiments : status report on results with aluminum stainless steel-304, uranium, and zircaloy-2 (Argonne National Laboratory, 1962), by Frank J. Testa, Marshall F. Deerwester, Richard O. Ivins, Robert C. Liimatainen, U.S. Atomic Energy Commission, and Argonne National Laboratory. Chemical Engineering Division (page images at HathiTrust) Review and correlation of in-pile zircaloy-2 corrosion data and a model for the effect of irradiation (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 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 (Hanford Atomic Products Operation, 1964), by R. C. Aungst, L. J. Defferding, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, and Hanford Atomic Products Operation (page images at HathiTrust) The effects of hot-water thermal treatments on the cold work recovery of Zircaloy-2 (Hanford Atomic Products Operation, 1964), by A. L. Bement, J. E. Irvin, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, and Hanford Atomic Products Operation (page images at HathiTrust) Oxide tenacity on alloys exposed to reactor coolants (Hanford Atomic Products Operation, 1963), by L. D. Perrigo, U.S. Atomic Energy Commission, and United States. Energy Research and Development Administration (page images at HathiTrust) High temperature oxidation of zirconium and Zircaloy-2 in oxygen and water vapor (Hanford Atomic Products Operation, 1962), by R. E. Westerman, Richard E. Westerman, U.S. Atomic Energy Commission, Hanford Atomic Products Operation, and Pacific Northwest Laboratory (page images at HathiTrust) Creep properties of zircaloy-2 for design application (Hanford Atomic Products Operation, 1962), by P. J. Pankaskie, 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 (Hanford Atomic Products Operation, 1963), by L. A. Hartcorn, Richard E. Westerman, 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 (Hanford Atomic Products Operation, 1963), by Arden Lee Jr Bement, 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. Part I (Hanford Atomic Products Operation, 1962), by L. J. Defferding, U.S. Atomic Energy Commission, Hanford Atomic Products Operation Reactor and Fuels Research and Development Operation, and Pacific Northwest Laboratory (page images at HathiTrust) In-reactor monitoring of zircaloy-2 PRTR pressure tubes. Part I, September, 1960--May, 1962 (Hanford Atomic Products Operation, 1962), by D. R. Doman, P. J. Pankaskie, 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 (Hanford Atomic Products Operation, 1962), by T. B. Correy, 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 (Hanford Atomic Products Operation, 1962), by L. C. Lemon, W. T. Ross, 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 (Hanford Atomic Products Operation, 1962), by R. L. Call, 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 (Hanford Atomic Products Operation, 1962), by R. C. Aungst, 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 (Hanford Atomic Products Operation, 1961), by H. P. Maffei, 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 (Hanford Atomic Products Operation, 1961), by W. G. Jr Magnuson, U.S. Atomic Energy Commission, Hanford Atomic Products Operation, and Pacific Northwest Laboratory (page images at HathiTrust) The activation energies for creep of zircaloy-2 (Hanford Atomic Products Operation, 1962), by J. J. Holmes, U.S. Atomic Energy Commission, Hanford Atomic Products Operation Reactor Fuels Research and Development Operation, and Pacific Northwest Laboratory (page images at HathiTrust) Evaluation of welded and seamless zirconium and zircaloy-2 tubing : final report (U.S. Atomic Energy Commission, 1958), by S. H. Bush, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Reactor and Fuels Research and Development Operation (page images at HathiTrust) Preferred orientations in extruded zircaloy-2 tubing (U.S. Atomic Energy Commission, 1960), by J. J. Laidler, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Reactor and Fuels Research and Development Operation (page images at HathiTrust) Ultrasonic inspection of PRTR fuel element cladding (U.S. Atomic Energy Commission, 1960), by P. L. Farnsworth, T. G. Lambert, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust) Recovery and recrystallization of zirconium and its alloys. Part 3, Annealing effects in zircaloy-2 and zircaloy-3 (Hanford Atomic Products Operation, 1961), by Spencer Harrison Bush, R. S. Kemper, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Reactor and Fuels Research and Development Operation (page images at HathiTrust) Annealing of warm-extruded zircaloy-2 to an ultrafine grain size (Hanford Atomic Products Operation, 1961), by R. L. Knecht, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Reactor and Fuels Research and Development Operation (page images at HathiTrust) A study of the wear and galling of autoclaved zircaloy-2 by various materials (U.S. Atomic Energy Commission, 1961), by J. W. Weber, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust) High frequency resistance welding of spacer ribs to zircaloy-2-clad UO₂ fuel components (U.S. Atomic Energy Commission, 1961), by L. R. Vancott, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust) Quality evaluation of zircaloy-2 sheath tubing (U.S. Atomic Energy Commission, 1959), by P. L. Farnsworth, R. B. Socky, H. P. Oakes, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust) Zircaloy-2 pilot plant etching and rinsing facility (Hanford Atomic Products Operation, 1959), by H. P. Maffei, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Reactor and Fuels Research and Development Operation (page images at HathiTrust) High temperature, high pressure nozzle-to-tube connections for the 1706 KER facility (U.S. Atomic Energy Commission, 1957), by D. R. Doman, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Reactor and Fuels Research and Development Operation (page images at HathiTrust) Evaluation of welded and seamless zirconium and zircaloy-2 tubing : interim report (U.S. Atomic Energy Commission, 1958), by S. H. Bush, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Reactor and Fuels Research and Development Operation (page images at HathiTrust) Interim report on the hydrostatic destructive testing of Zircaloy-2 pressure tubing (U.S. Atomic Energy Commission, 1959), by V. E. Kahle, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Reactor and Fuels Research and Development Operation (page images at HathiTrust) Hydrogen effects on Zircaloy-2 tensile properties (U.S. Atomic Energy Commission, 1959), by H. H. Burton, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, Hanford Atomic Products Operation. Reactor and Fuels Research and Development Operation, and Hanford Atomic Products Operation (page images at HathiTrust) End closure for plutonium bearing Zircaloy-2-clad fuel elements (U.S. Atomic Energy Commission, 1959), by L. C. Lemon, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Reactor and Fuels Research and Development Operation (page images at HathiTrust) A review of the properties of Zircaloy-2 (U.S. Atomic Energy Commission, 1959), by G. E. Zima, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Research and Engineering Operation (page images at HathiTrust) Preparing Zircaloy-2 for autoclave testing : the pickling and rinsing process (U.S. Atomic Energy Commission, 1959), by D. W. Shannon, B. Griggs, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Reactor and Fuels Research and Development Operation (page images at HathiTrust) Interim report on creep characteristics of Zircaloy-2 (U.S. Atomic Energy Commission, 1959), by P. J. Pankaskie, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Reactor and Fuels Research and Development Operation (page images at HathiTrust) Notch slow-bend testing of zircaloy-2 (Hanford Atomic Products Operation, 1956), by R. G. Wheeler, U.S. Atomic Energy Commission, Hanford Atomic Products Operation, and Pacific Northwest Laboratory (page images at HathiTrust) Electrolytic disintegration of zircaloy-2 in nitric acid solutions (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) Hydrofluoric acid decladding of zirconium-clad power reactor fuel elements (Oak Ridge National Laboratory, 1958), by W. E. Clark, A. H. Kibbey, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Chemical Technology Division. Chemical Development Section B. (page images at HathiTrust) Nuclear analyses of the N.S. Savannah reactor with Zircaloy or stainless steel as fuel-element containers (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) Review of zircaloy-2 and zircaloy-4 properties relevant to N.S. Savannah reactor design (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) Metallurgy of zircaloy-2 : Part II The effects of fabrication variables on the preferred orientation and anisotropy of strain behavior (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) Zirflex process for PWR blanket fuel : [Part] II Revised flowsheet (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) Metallurgy of zircaloy-2 : Part I The effects of fabrication variables on the anisotropy of mechanical properties (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 (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) 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 (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) Zirconium concentration measurements in the PRTR primary coolant : interim report, December 8, 1962 - June 30, 1963 (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] (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) The nitric-hydrofluoric acid pickling of zircaloy-2 (Battelle Memorial Institute ;, 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 (Battelle Memorial Institute ;, 1959), by Arthur P. Young, Charles M. Schwartz, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust) Effect of high boron burnups on B₄C and ZrB₂ dispersions in Al₂O₃ and Zircaloy-2 (Battelle Memorial Institute ;, 1963), by Richard J. Burian, John E. Gates, Earle Fromm, Battelle Memorial Institute, and U.S. Atomic Energy Commission (page images at HathiTrust) Stress relaxation in zircaloy-2 during irradiation at less than 100©�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) Design and fabrication of fuel rods clad with stainless-steel-lined zircaloy-2 (U.S. Atomic Energy Commission, Division of Technical Information, 1964), by C. J. Baroch, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust) Development of zircaloy-clad, discrete burnable poison elements for S3G/S4G (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) Development and properties of coextruded zircaloy-clad uranium fuel elements with integral end seals (Oak Ridge, Tennessee : United States Atomic Energy Commission, Office of Technical Information, 1958., 1958), 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 (Oak Ridge, Tennessee : United States Atomic Energy Commission, Office of Technical Information, 1958., 1958), by H. F. Sawyer, Inc Nuclear Metals, and U.S. Atomic Energy Commission (page images at HathiTrust) Effect of hydrogen on the strain fatigue properties of zircaloy-2 weld metal (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) Diffusion annealing as a means of improving corrosion resistance of zircaloy-2 clad, uranium-2 w/o zirconium rods (Oak Ridge, Tennessee : United States Atomic Energy Commission, Office of Technical Information, 1960., 1960), 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 (Oak Ridge, Tennessee : United States Atomic Energy Commission, Office of Technical Information, 1960., 1960), by V. Nerses, Inc Nuclear Metals, and U.S. Atomic Energy Commission (page images at HathiTrust) Irradiation of UO₂ fuel rods : the X-1-L experiment (Pittsburgh, Pennsylvania. : Bettis Atomic Power Laboratory, 1960., 1960), 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 (Pittsburgh, Pennsylvania : Bettis Atomic Power Laboratory, 1959., 1959), 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 (Washington, D.C. : Office of Technical Services, Department of Commerce, 1957., 1957), by Richard M. Lieberman, U.S. Atomic Energy Commission, Westinghouse Electric Corporation, and Bettis Atomic Power Laboratory (page images at HathiTrust) An assessment of the long-term storage of zircaloy fuel rods in water : final report (California Energy Commission, 1977), by Zuhair A Munir and California Energy Commission (page images at HathiTrust) Thin wall tubing tests using ultrasonic shear waves. Part II, Production test equipment, its operation and test results (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) Fabrication of the Plutonium Recycle Test Reactor zircaloy-2 high pressure process tubes (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) In-reactor monitoring of zircaloy-2 PRTR pressure tubes. Part II, May and June, 1962 (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) In-reactor monitoring of zircaloy-2 PRTR pressure tubes. Part III, July 1963 - November 1963 (Hanford Atomic Products Operation, 1963), by P. J. Pankaskie, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust) Inert tungsten-arc welding of S3G zircaloy channel sections (Schenectady, New York : General Electric Company, Knolls Atomic Power Laboratory, 1956., 1956), by S. A. Toftegaard, Knolls Atomic Power Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
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