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Nuclear fuel claddings

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• Metal cladding
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• Claddings, Nuclear fuel

• Effect of long-time, elevated-temperature exposures to vacuum and lithium on the properties of a tantalum alloy, T-111 / (Washington, D.C. : National Aeronautics and Space Administration ; [Springfield, Va. : For sale by the National Technical Information Service], 1974), by Robert J. Buzzard, Keith D. Sheffler, and Lewis Research Center (page images at HathiTrust)
• Evaluation of tantalum-alloy-clad uranium mononitride fuel specimens from 7500-hour, 1040 ̊C pumped-lithium-loop test / (Washington, D.C. : National Aeronautics and Space Administration ; [Springfield, Va. : For sale by the National Technical Information Service], 1974), by Gordon K. Watson and Lewis Research Center (page images at HathiTrust)
• Effect of nitrogen on tensile properties and structures of T-111 (tantalum - 8-percent-tungsten - 2-percent-hafnium) tubing / (Washington, D.C. : National Aeronautics and Space Administration ; [Springfield, Va. : For sale by the National Technical Information Service], 1973), by Robert J. Buzzard, Robert R. Metroka, and Lewis Research Center (page images at HathiTrust)
• Thermal-expansion method for lining tantalum alloy tubing with tungsten / (Washington, D.C. : National Aeronautics and Space Administration ; [Springfield, Va. : For sale by the National Technical Information Service], 1973), by Gordon K. Watson, William F. Mattson, J. Daniel Whittenberger, and Lewis Research Center (page images at HathiTrust)
• Irradiation of an aluminum alloy-clad ceramic pellet-fueled plate / (Argonne, Ill. : Argonne National Laboratory, Reactor Engineering Division, 1960), by A. P. Gavin and Argonne National Laboratory (page images at HathiTrust)
• Irradiation of an aluminum alloy-clad, aluminum-uranium alloy-fueled plate / (Argonne, Ill. : Argonne National Laboratory, Reactor Engineering Division, 1960), by A. P. Gavin, C. C. Crothers, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
• Design, construction, and initial operation of General Atomic in-pile loop / (San Diego, Calif. : General Atomic Division of General Dynamics, [1965]), by R. H. Simon, U.S. Atomic Energy Commission, and General Dynamics Corporation. General Atomic Division (page images at HathiTrust)
• Recoil activity from stainless-steel cladding : a major contribution to coolant-stream radioactivity in GCR-2 / (Oak Ridge, Tenn. : Massachusetts Institute of Technology, Engineering Practice School, 1959), by W. L. Brassert, F. H. Morse, G. K. Gardiner, U.S. Atomic Energy Commission, and Massachusetts Institute of Technology. Engineering Practice School (page images at HathiTrust)
• Second annual report on permeability of cladding materials to inert gases / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Office of Technical Information, 1960), by G. T. Murray, U.S. Atomic Energy Commission. Technical Information Service, and Materials Research Corporation (page images at HathiTrust)
• Analysis of failure of type 304 stainless steel clad swaged powder fuel assembly / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Division of Technical Information, 1963), by E. A. Lees, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• The fabrication of clad massive UO₂ fuel elements by coextrusion / (Oak Ridge, Tenn. : United States Atomic Energy Commission, Office of Technical Information, 1960), by F. S. Gardner, J. G. Hunt, Inc Nuclear Metals, and U.S. Atomic Energy Commission (page images at HathiTrust)
• The effect of deionized water on reactor effluent activities. (Richland, Wash. : Hanford Atomic Products Operation, 1964), by W. B. Silker, C. W. Thomas, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
• Tensile properties from room temperature to 1315 ̊C of tungsten-lined tantalum-alloy (T-111) tubing fabricated by hot isostatic pressing / (Washington, D.C. : National Aeronautics and Space Administration ; [Springfield, Va. : For sale by the National Technical Information Service], 1974), by Robert J. Buzzard, Robert R. Metroka, and Lewis Research Center (page images at HathiTrust)
• Off-design temperature effects on nuclear fuel pins for an advanced space-power-reactor concept / (Washington, D.C. : National Aeronautics and Space Administration ; [Springfield, Va. : For sale by the National Technical Information Service], 1974), by Kenneth J. Bowles and Lewis Research Center (page images at HathiTrust)
• Electrical heating tests of uranium dioxide external fuel configuration at emitter temperature of 1900 K / (Washington, D.C. : National Aeronautics and Space Administration ; [Springfield, Va. : For sale by the National Technical Information Service], 1974), by Dominic C. DiIanni, John T. Mayer, and Lewis Research Center (page images at HathiTrust)
• Causes, measurement, and elimination of fuel-element fission product leakage at the NASA Plum Brook reactor / (Washington, D.C. : National Aeronautics and Space Administration ; Springfield, Va. : For sale by the Clearinghouse for Federal Scientific and Technical Information, [1969]), by A. Bert Davis, Richard H. Brickley, and Lewis Research Center (page images at HathiTrust)
• Simplified analysis of nuclear fuel pin swelling / (Washington, D.C. : National Aeronautics and Space Administration ; [Springfield, Va. : For sale by the Clearinghouse for Federal Scientific and Technical Information, 1970]), by Armin F. Lietzke and Lewis Research Center (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)
• PBF severe fuel damage test 1-3 test results report / (Washington, DC : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : For sale by the Supt. of Docs., U.S. G.P.O., 1989), by Zoel R. Martinson, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research, EG & G Idaho, and Idaho National Engineering Laboratory (page images at HathiTrust)
• Data report for the instrumented fuel assembly IFA-513 / (Washington, D.C. : The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1981), by E. R. Bradley, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• Nuclear fuel rod behavior during normal and abnormal operating conditions-results of test PR-1 / (Idaho Falls, Idaho : EG & G Idaho, Inc., 1981), by Richard W. Garner, Richard H. Smith, Daniel T. Sparks, U.S. Nuclear Regulatory Commission, and Inc EG & G (page images at HathiTrust; US access only)
• Fuel rod failure as a consequence of departure from nucleate boiling or dryout / (Washington, D.C. : Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission ; Springfield, Va. : Available from National Technical Information Service, 1979), by Robert Van Houten and U.S. Nuclear Regulatory Commission. Fuel Behavior Research Branch (page images at HathiTrust)
• FRAP-T4 best estimate sensitivty study / (Washington, D.C. : The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1980), by B. L. Hansen, EG & G Idaho, and U.S. Nuclear Regulatory Commission. Division of Systems Safety (page images at HathiTrust)
• Evaluation of simulated-LOCA tests that produced large fuel cladding ballooning / (Washington : Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Systems Safety, Core Performance Branch, 1979), by D. A. Powers, R. O. Meyer, and U.S. Nuclear Regulatory Commission. Division of Systems Safety. Core Performance Branch (page images at HathiTrust)
• Control rod guide tube wear in operating reactors : operating experience report / (Washington, D.C. : The Commission, 1980), by R. Riggs and U.S. Nuclear Regulatory Commission. Division of Operating Reactors (page images at HathiTrust)
• Fracture evaluation of surface cracks embedded in reactor vessel cladding : unirradiated bend specimen results / (Washington, D.C. : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), by D. E. McCabe, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering, and Materials Engineering Associates (page images at HathiTrust)
• Plan for experimental characterization of clad vessel steel after irradiation / (Washington, D.C. : Division of Engineering Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986), by D. E. McCabe, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Safety, and Materials Engineering Associates (page images at HathiTrust)
• Light-water-reactor safety fuel systems research programs : quarterly progress report / (Washington, D.C. : Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1985-), by U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation and Argonne National Laboratory (page images at HathiTrust)
• Mechanistic considerations used in the development of the PROFIT PCI failure model / (Washington, D.C. : The Commission, 1980), by P. J. Pankaskie, U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Systems Integration, and Pacific Northwest Laboratory (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)
• FRAP-T5 uncertainty study of five reactor transient and accident events / (Washington, D.C. : The Division : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1981), by E. T. Laats, B. L. Hansen, EG & G Idaho, and U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Systems Integration (page images at HathiTrust)
• Reactivity initiated accident test series test RIA 1-2 fuel behavior report / (Washington, D.C. : U.S. Nuclear Regulatory Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1981), by Beverly A. Cook, Idaho National Engineering Laboratory, United States. Department of Energy. Idaho Operations Office, U.S. Nuclear Regulatory Commission, and EG & G Idaho (page images at HathiTrust)
• Multirod burst test program progress report for ... /, by Oak Ridge National Laboratory. Engineering Technology Division. issuing body and sponsor U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research (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)
• Postirradiation examination results for the irradiation effects test IE-1 /, by Arthur S. Mehner, R. Scott Semken, U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation, EG & G Idaho, United States. Department of Energy. Idaho Operations Office, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• Fabrication of zirconium-clad uranium fuel elements /, by P. Loewenstein, sponsor Massachusetts Institute of Technology, and sponsor U.S. Atomic Energy Commission (page images at HathiTrust)
• SNAP 8 development reactor nuclear analysis /, by L. D. Swenson, U.S. Atomic Energy Commission, and Rockwell International. Atomics International Division (page images at HathiTrust)
• Biaxial creep and stress rupture of wire-wrapped cladding in 1200[degrees]F sodium under [delta]T conditions : interim report /, by J. H. Shively, U.S. Atomic Energy Commission, and Rockwell International. Atomics International Division (page images at HathiTrust)
• Investigation of vapor phase plating for cladding reactor fuels (literature search) /, by J. Bodine, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (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)
• 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)
• Effect of oxide dissolution and heat transfer on the corrosion of aluminum fuel cladding / (Richland, Wash. : Hanford Atomic Products Operation, 1963), by D. R. Dickinson, R. J. Lobsinger, 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)
• Decladding of Consolidated Edison Power reactor fuel by Sulfex and Darex processes : cyclic dissolution experiments / (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1960), by L. M. Ferris, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Chemical Technology Division. Chemical Development Section B. (page images at HathiTrust)
• Diffusion in the stabilized zirconia-urania system / ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by D. R. Mash, Reese S. Kern, K. K. Ikeuye, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Experimental and analytical reactivity studies of clean critical stainless steel cores / ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1961]), by A. H. Spano, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Nondestructive inspection of EBR-II fuel-jacket tubing using electromagnetic techniques / (Lemont, Ill. : Argonne National Laboratory, Special Materials and Services Division, 1967), by Thomas H. Busse, Norman S. Beyer, D. R. Wood, U.S. Atomic Energy Commission, and Argonne National Laboratory. Special Materials and Services Division (page images at HathiTrust)
• Aluminum decladding procedure by the volatization of aluminum chloride / (Livermore, Ca. : [Lawrence] Radiation Laboratory, 1954), by W. W. T. Crane, M. S. Coops, G. H. Higgins, Lawrence Radiation Laboratory, and U.S. Atomic Energy Commission (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)
• Aluminum corrosion in subcritical and zero power critical reactors / (Aiken, S.C. : E.I. Du Pont de Nemours & Company, Savannah River Laboratory, 1964), by Mack E. Bergstresser, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Hydrogen detector for monitoring uranium cladding failures / (Aiken, S.C. : E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, [1961]), by Robert L. Hooker, E. J. Hennelly, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Fabrication quality of HWCTR driver tubes / (Aiken, S.C. : E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, [1962]), by Richard C. Pugh, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Remarks concerning materials for nuclear superheat fuel cladding / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Division of Technical Information, 1962), by K. C. Antony, M. B. Reynolds, W. V. Cummings, D. L. Douglass, H. H. Klepfer, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Fuel element development for Piqua OMR / (Canoga Park, California : Atomics International, [1960]), by M. H. Binstock, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Fuel cladding failure monitor for sodium reactors / (Canoga Park, California : Atomics International, [1964]), by R. J. Hall, E. A. Moore, R. E. Avery, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Fuel element development program for the pebble bed reactor : phase I progress report [for] May 1, 1959 to October 31, 1959., by U.S. Atomic Energy Commission. New York Operations Office and Inc Sanderson & Porter (page images at HathiTrust)
• Joining of APM aluminum alloys for reactor fuel applications /, by E. C. Supan, G. V. Alm, W. H. Friske, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Isostatic pressing of UO₂ in high temperature metals /, by I. Sheinhartz, J. Fugardi, Sylvania-Corning Nuclear Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Chemical replacement plating of zircaloy /, by C. R. Woods, T. R. Padden, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• BWR blowdown/emergency core cooling sixteenth quarterly progress report : October 1 - December 31, 1979 /, by Stanley Caruso, General Electric Company. Nuclear Engineering Division, Electric Power Research Institute, U.S. Nuclear Regulatory Commission, United States Government Printing Office, and United States. National Technical Information Service (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)
• 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)
• Erosion resistance of swaged UO₂ following an in-reactor fuel rod cladding failure / (Richland, Wash. : Hanford Atomic Products Operation, 1961), by M. K. Millhollen, J. L. Bates, G. R. Horn, 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)
• 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)
• Fabrication of aluminum clad plutonium-aluminum alloy pin elements / (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by L. C. Lemon, W. T. Ross, 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 aluminum for use in reactors cooled by high-temperature recirculating water / (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by J. A. Ayres, 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)
• 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)
• Development of the Sulfex process for decladding stainless-steel-clad power reactor fuel elements with sulfuric acid / (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1959), by A. H. Kibbey, J. H. Goode, W. E. Clark, J. R. Flanary, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Chemical Technology Division. Chemical Development Section B. (page images at HathiTrust)
• Mechanical cladding-fuel interactions during thermal cycling of metal-clad fuel elements / (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1965), by W. R. Martin, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Metals and Ceramics Division (page images at HathiTrust)
• Effect of heat flux on the corrosion of aluminum by water. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1964), by J. C. Griess, J. L. English, H. C. Savage, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Reactor Chemistry Division (page images at HathiTrust)
• Mechanical properties of X8001 and 6061 aluminum alloys and aluminum-base fuel dispersion at elevated temperatures / (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1964), by W. R. Martin, J. R. Weir, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Metals and Ceramics Division (page images at HathiTrust)
• Sulfex-thorex and darex-thorex processes for the dissolution of consolidated edison power reactor fuel : laboratory development / (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1960), by L. M. Ferris, A. H. Kibbey, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory Chemical Technology Division Chemical Development Section B. (page images at HathiTrust)
• Fuel rod experience during the Spert I destructive test series with a stainless steel clad, rod-type core / ([Idaho Falls, Idaho] : Idaho Operations Office, U.S. Atomic Energy Commission, 1965), by J. Dugone, D. D. Wieland, Phillips Petroleum Company. Atomic Energy Division, U.S. Atomic Energy Commission. Idaho Operations Office, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Measurement of fission product leakage from fuel elements stored in water / ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1965), by D. W. Rhodes, Idaho Chemical Processing Plant, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Damage to stainless steel fuel in SPERT reactors / ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1961]), by R. E. Heffner, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Diffusion of xenon through aluminum and stainless steel / (Upton, N.Y. : Brookhaven National Laboratory, 1960), by A. W. Castleman, A. M. Eshaya, F. E. Hoffmann, U.S. Atomic Energy Commission, Brookhaven National Laboratory, and Inc Associated Universities (page images at HathiTrust)
• Chemical decladding of stainless steel fuel elements in a stainless steel dissolver : progress report no. 1 / (Upton, N.Y. : Brookhaven National Laboratory, 1962), by Herbert M. Katz, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (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)
• Fabrication of boral control plates for Kiwi reactors / (Los Alamos, N.M. : Los Alamos Scientific Laboratory of the University of California, 1962), by R. W. Keil, G. S. Hanks, U.S. Atomic Energy Commission, and Los Alamos Scientific Laboratory (page images at HathiTrust)
• Potential measurements of aluminum-clad uranium systems / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Technical Information Service, 1955), by Arch B. Tripler, Charles L. Faust, John G. Beach, Battelle Memorial Institute, and U.S. Atomic Energy Commission. Technical Information Service (page images at HathiTrust)
• Electrocladding of zirconium with platinum / (Columbus, OH : Battelle Memorial Institute, [1956]), by Arch B. Tripler, Charles L. Faust, John G. Beach, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Study of bonding fundamentals / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from the Office of Technical Service, U.S. Dept. of Commerce, [1956]), by Robert Isaac Jaffee, James B. Melehan, James E. Reynolds, Horace R. Ogden, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Gas-pressure bonding of flat-plate fuel assemblies / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from Office of Technical Services, U.S. Dept. of Commerce, [1959]), by Ralph W. Getz, Charles B. Boyer, Edwin S. Hodge, Stan J. Paprocki, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Alumina-clad UO₂ for fuel applications / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from Office of Technical Services, U.S. Dept. of Commerce, [1959]), by Allison K. Smalley, Winston H. Duckworth, W. C. Riley, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Irradiation of clad graphite in high-temperature high-pressure CO₂ / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from Office of Technical Services, U.S. Dept. of Commerce, [1959]), by William H. Goldthwaite, Ward S. Diethorn, William E. Murr, John C. Smith, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Corrosion of stainless alloys in high-temperature nitrogenous environments / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from Office of Technical Services, U.S. Dept. of Commerce, [1959]), by Ward S. Diethorn, Donald L. Keller, Battelle Memorial Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Gas-pressure bonding of zircaloy-clad flat-plate uranium dioxide fuel elements / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from Office of Technical Services, U.S. Dept. of Commerce, [1959]), by Paul J. Gripshover, Donald C. Carmichael, Edwin S. Hodge, Stan J. Paprocki, 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)
• Effects of yttrium on the fabrication and tensile properties of two modified stainless 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)
• Dissolution of irradiated consolidated Edison power-reactor fuel by the Sulfex and Darex processes / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from Office of Technical Services, U.S. Dept. of Commerce, [1960]), by R. A. Ewing, Duane Neuman Sunderman, Harvey B. Brugger, Battelle Memorial Institute, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory. Chemical Technology Division (page images at HathiTrust)
• Further development of gas-pressure bonding of zircaloy-clad flat-plate uranium dioxide fuel elements / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from Office of Technical Services, U.S. Dept. of Commerce, [1960]), by Donald C. Carmichael, Paul J. Gripshover, Edwin G. Wintucky, Edwin H. Layer, Edwin S. Hodge, Stan J. Paprocki, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• High-temperature niobium-base alloys for sodium-cooled reactors / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from the Office of Technical Services, U.S. Dept. of Commerce, [1961]), by John A. DeMastry, Ronald F. Dickerson, Frederic R. Shober, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Irradiation-capsule study for SM-2 reference and alternate dispersion fuels / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from the Office of Technical Services, U.S. Dept. of Commerce, [1961]), by John H. Stang, Euguene M. Simons, John F. Lagedrost, David B. Hamilton, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Incorporation of a boron burnable poison and spherical UO₂ in SM-2 stainless-matrix fuel plates / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from the Office of Technical Services, U.S. Dept. of Commerce, [1961]), by Andrew K. Foulds, G. W. Cunningham, D. L. Keller, Stan J. Paprocki, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Fabrication and irradiation of SM-2 core materials / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from the Office of Technical Services, U.S. Dept. of Commerce, [1961]), by Donald E. Lozier, William E. Murr, G. W. Cunningham, Ronald F. Dickerson, Stan J. Paprocki, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Sulfex-thorex and darex-thorex dissolution of high-burnup consolidated edison reactor fuel / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from Office of Technical Services, U.S. Dept. of Commerce, [1961]), by R. A. Ewing, Duane Neuman Sunderman, Harvey B. Brugger, Battelle Memorial Institute, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory. Chemical Technology Division (page images at HathiTrust)
• Evaluation of irradiated alumina-coated UO₂ particles dispersed in graphite spheres / (Columbus, Ohio : Battelle Memorial Institute, [1962]), by Ronald F. Dickerson, John E. Gates, R. L. Ritzman, Richard J. Burian, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Radiation stability of compacts of aluminum and fuel-bearing glass fibers / (Columbus, Ohio : Battelle Memorial Institute, [1962]), by Richard J. Burian, Ronald F. Dickerson, John E. Gates, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Thermodynamics for compatibility studies of metal-clad uranium carbide / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from Office of Technical Services, U.S. Dept. of Commerce, 1962), by G. W. Cunningham, Carl A. Alexander, James J. Ward, Battelle Memorial Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Use of agglomerated UO₂ in pressure-bonded stainless steel-clad fuel rods / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from Office of Technical Services, U.S. Dept. of Commerce, 1963), by Robert J. Diersing, Charles B. Boyer, Stanldey W. Porembka, Edwin S. Hodge, Battelle Memorial Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Parametric studies of fuel pin temperature response / ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1969), by S. E. Jensen, Idaho National Reactor Testing Station, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
• A cladding thickness tester for flat fuel elements / (Oak Ridge, Tenn. : United States Atomic Energy Commission, Technical Information Service Extension, [1957]), by J. D. Ross, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust; US access only)
• Processing of fuel assemblies that contain zirconium / (Aiken, S.C. : E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, [1959]), by Woodfin E. Shuler, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Metal-water reactions. (San Jose, Calif. : General Electric Company, Atomic Power Equipment Dept. ; Washington, D.C. : Available from the Office of Technical Services, Dept. of Commerce, [1959]), by K. M. Horst, U.S. Atomic Energy Commission, and General Electric Company (page images at HathiTrust)
• Plastic strain in thin fuel element cladding due to UO₂ thermal expansion / (Pittsburgh, Pa. : General Electric Co., Atomic Power Equipment Dept., 1961), by M. F. Lyons, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Slow cycle strain fatigue in thin wall tubing : preliminary report / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Division of Technical Information, 1962), by M. B. Reynolds, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Examination of 304 stainless steel cladding from cold-swaged and rolled fuel rods / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Division of Technical Information, 1962), by W. V. Cummings, R. E. Blood, D. R. Lewis, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Erosion flow testing of purposely defected stainless steel clad compacted UO₂ powder fuel / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Division of Technical Information, 1962), by J. W. Lingafelter, R. J. Seely, E. A. Lees, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Evaluation of 300 series stainless steel tubing for fuel cladding / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Division of Technical Information, 1962), by R. F. Kirby, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Evaluation of zirconium 1.5 w/o niobium cladding for use in boiling water reactor environments / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Division of Technical Information, 1962), by W. C. Rous, C. J. Baroch, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Microstructural evaluation of superheat cladding materials / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, 1965), by F. A. Comprelli, J. E. Lewis, U.S. Atomic Energy Commission, and General Electric Company. Atomic Power Equipment Department (page images at HathiTrust)
• Progress report on photoelastic study of cladded tubes / (Cincinnati, Ohio : General Electric, Aircraft Nuclear Propulsion Dept., 1961), by R. Guernsey, General Electric Company, and U.S. Atomic Energy Commission (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)
• Zirconium moderator cladding irradiated in the Sodium Reactor Experiment / (Canoga Park, California : Atomics International, [1960]), by J. J. Gill, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Radiation effects resulting from fuel cladding failure in the 45.5 Mw (Thermal) organic moderated reactor / (Canoga Park, California : Atomics International, [1959]), by M. Dunenfeld, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Compatibility of uranium carbide fuels with cladding materials /, by P. E. Elkins, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• A study of uranium carbide and cladding materials for high-temperature sodium-cooled reactors /, by R. D. Hahn, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Development of niobium diffusion barriers for aluminum-clad uranium alloy fuel elements /, by B. N. Briggs, W. H. Friske, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Magnetic pulse swaging of APM-UOb2s fuel rods /, by E. C. Supan, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Diffusion kinetics studies in the Al-Ni-U system /, by R. A. Harlow, Otto Gamba, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• SNAP technology handbook /, by G. F. Burdi, D. H. Stone, A. K. Smalley, R. E. Johnson, G. G. Bentle, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Fuel element development program for the pebble bed reactor : phase II summary report [covering the period] November 1, 1959 to October 31, 1960., by U.S. Atomic Energy Commission. New York Operations Office and Inc Sanderson & Porter (page images at HathiTrust)
• Ultrasonic filling of tubular cladding : applications of ultrasonic energy /, by William B. Tarpley, Richard Pheasant, U.S. Atomic Energy Commission. New York Operations Office, and Aeroprojects Incorporated (page images at HathiTrust)
• The fabrication of clad massive UOb2s fuel elements by coextrusion..., by Inc Nuclear Metals and U.S. Atomic Energy Commission. Division of Reactor Development (page images at HathiTrust)
• Wound and folded single-sheet fuel elements : final technical report to the United States Atomic Energy Commission for the period July 1, 1960 through June 30, 1961 /, by R. G. Jenkins, J.M. Siergiej, A.R. Gilman, E.F. Jordan, Inc Nuclear Metals, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Columbium alloy clad uranium carbide fuel element : final report [covering the period] May 1, 1959-April 30, 1960 /, by J.J. Finley, S. Sarian, M. Korchynsky, U.S. Atomic Energy Commission, and Union Carbide Corporation. Metals Division (page images at HathiTrust)
• Columbium alloy clad uranium carbide fuel element : technical report no. 61-33 /, by M. Korchynsky, H.J. Brown, S.S. Sarian, J.L. Wilson, J.J. Finley, U.S. Atomic Energy Commission, and Union Carbide Metals Company (page images at HathiTrust)
• Effects of high burnup on zircaloy-clad, bulk UO₂, plate fuel element samples /, by R. C. Daniel, W. Yeniscavich, H. B. Meieran, M. L. Bleiberg, 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)
• Interdiffusion studies for fuel-cladding compatibility in IFR fuels /, by D. D. Keiser, M. A. Dayananda, issuing body University of Chicago, and issuing body Argonne National Laboratory (page images at HathiTrust)
• Biaxial stress-rupture properties of austenitic stainless steels in zirconium-gettered sodium /, by W. T. Lee, U.S. Atomic Energy Commission, and North American Aviation. Atomics International 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)
• Multirod burst test program : progress report / (Oak Ridge, Tennessee. : Dept. of Energy [Office of Energy Technology], Oak Ridge National Laboratory ; Springfield, Virginia. : For sale by the National Technical Information Service, 1978-), by R. H. Chapman, Oak Ridge National Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research (page images at HathiTrust; US access only)
• BWR blowdown/emergency core cooling fourteenth quarterly report : April 1-June 30, 1979 /, by D. L. Galyardt, General Electric Company. Nuclear Engineering Division, Electric Power Research Institute, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• BWR blowdown/emergency core cooling, fifteenth quarterly progress report, July 1-September 30, 1979 /, by Ramal Muralidharan, General Electric Company. Nuclear Engineering Division, Electric Power Research Institute, U.S. Nuclear Regulatory Commission, United States. National Technical Information Service, and United States Government Printing Office (page images at HathiTrust)
• PBF LOCA test LOC-6 fuel behavior report /, by James M Broughton, Philip E. MacDonald, Daniel W. Golden, Donald L. Hagrman, Krishna Vinjamuri, Idaho National Engineering Laboratory, EG & G Idaho, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• Charpy toughness and tensile properties of a neutron-irradiated stainless steel submerged arc weld cladding overlay /, by W. R Corwin, R. K. Nanstad, R. G. Berggren, Oak Ridge National Laboratory. Metals and Ceramics Division, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research (page images at HathiTrust)
• Detection of small-sized near-surface under-clad cracks for reactor pressure vessels /, by T. T. Taylor, G. J. Posakony, S. R. Doctor, S. L. Crawford, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology (page images at HathiTrust)
• Experiment data report for multirod burst test (MRBT) bundle B-4 /, by A. W Longest, J. L. Crowley, R. H. Chapman, Oak Ridge National Laboratory. Engineering Technology Division, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research (page images at HathiTrust)
• Sampling blanks for the LMFBR cladding program /, by E. W. Murbach, North Amercian Aviation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Fission-product-release measurement from clad fuel specimens / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from Office of Technical Services, U.S. Dept. of Commerce, 1962), by Ronald F. Dickerson, Frank A. Rough, Arthur A. Bauer, Mihkel Kangilaski, Battelle Memorial Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Experiment operations plan for a loss-of-coolant accident simulation in the National Research Universal Reactor : materials tests 1 and 2 / (Washington, D.C. : The Commission, 1981), by G. E. Russcher, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• Dosimetry methods for fuels, cladding, and structural materials : proceedings of the second ASTM-EURATOM Symposium on Reactor Dosimetry, Palo Alto, California, October 3-7, 1977. ([Washington, D.C.] : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [1977?]), by Calif.) ASTM-EURATOM Symposium on Reactor Dosimetry (2nd : 1977 : Palo Alto, International Atomic Energy Agency, United States. Nculear Regulatory Commission, Electric Power Research Institute, Euratom. Working Group on Reactor Dosimetry, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, and American Society for Testing and Materials. Subcommittee E10.05 on Dosimetry (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)
• Ultrasonic tube drawing: niobium, zircaloy-2, and copper /, by William B. Tarpley, Richard Pheasant, U.S. Atomic Energy Commission. New York Operations Office, and Aeroprojects Incorporated (page images at HathiTrust)
• Instability phenomena in thin-walled cylinders /, by W. R. Russ, Frederick Forscher, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Cost estimate for remote refabrication of metallic fuels /, by J. E Ayer, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
• Permeability of cladding materials to inert gases (Yonkers, N.Y. : Materials Research Corp. ; Oak Ridge, Tenn. : distributed by the U.S. Atomic Energy Commission, Office of Technical Information, 1959-), by U.S. Atomic Energy Commission. Technical Information Service and Materials Research Corporation (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)
• BWR blowdown/emergency core cooling twenty-first quarterly progress report, January 1 - April 17, 1981 /, by S. A Domning, General Electric Company. Nuclear Engineering Division, Electric Power Research Institute, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation, United States Government Printing Office, and United States. National Technical Information Service (page images at HathiTrust)
• Relaxation times and magnitudes in the thermal bowing of fuel element jackets / (Schenectady, N.Y. : Knolls Atomic Power Laboratory, General Electric Company, 1957), by W. C. Cohen, J. K. Davidson, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust; US access only)
• 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)
• Aluminum-electrocladding studies for proposed OMR fuel elements / (Canoga Park, California : Atomics International, [1958]), by G. V. Alm, M. H. Binstock, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Removal of irradiated UOb2s fuel from the cladding by controlled oxidation / (Canoga Park, California : Atomics International, [1959]), by L. A. Hanson, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Experiment operations plan for a loss-of-coolant accident simulation in the National Research Universal Reactor : materials test 2 /, by G. E Russcher, M. E. Cunningham, J. O. Barner, L. J. Parchen, C. L. Wilson, C. L. Mohr, R. K. Marshall, G. M. Hesson, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• Experiment operations plan for the MT-3 experiment in the NRU reactor /, by G. E Russcher, M. D. Freshley, L. J. Parchen, Charles L. Wilson, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Technology (page images at HathiTrust)
• Measured in-reactor data and postirradiation observations for IFA-527 /, by M. E Cunningham, D. D. Lanning, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• Modification of OCA-I for application to a reactor pressure vessel with cladding on the inner surface /, by A Sauter, S. K. Iskander, R. D. Cheverton, Oak Ridge National Laboratory. Engineering Technology Division, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research (page images at HathiTrust)
• Data summary report for fission product release test HI-4 /, by M. F Osborne, C. S. Webster, J. R. Travis, K. S. Norwood, R. A. Lorenz, J. L. Collins, Oak Ridge National Laboratory. Chemical Technology Division, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research (page images at HathiTrust)
• Cladding swelling and rupture models for LOCA analysis /, by D. A. Powers, R. O. Meyer, and U.S. Nuclear Regulatory Commission. Division of Systems Safety (page images at HathiTrust)

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