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Nuclear fuel rods

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• Nuclear fuel elements

• Nuclear fuel rods -- Analysis
• Nuclear fuel rods -- Calibration
• Nuclear fuel rods -- Computer programs
• Nuclear fuel rods -- Computer simulation
• Nuclear fuel rods -- Data processing
• Nuclear fuel rods -- Defects
• Nuclear fuel rods -- Design and construction
• Nuclear fuel rods -- Economic aspects
• Nuclear fuel rods -- Effect of radiation on
• Nuclear fuel rods -- Evaluation
• Nuclear fuel rods -- Experiments
• Nuclear fuel rods -- Materials
• Nuclear fuel rods -- Mathematical models
• Nuclear fuel rods -- Safety measures
• Nuclear fuel rods -- Testing
• Nuclear fuel rods -- Thermal properties
• Nuclear fuel rods -- Transportation

• Fuel rods, Nuclear
• Reactor fuel rods
• Rods, Nuclear fuel

• Textures in Rolled Uranium Rod (declassified edition; Oak Ridge, TN: U.S. Atomic Energy Commission, Technical Information Service, 1956), by W. P. Chernock and L. W. Kates (page images at HathiTrust)
• Assessment of FRAPCON-1 BE/EM calculated fission gas release in RISO fuel rods (The Commission :, 1980), by R. Chambers, E. T. Laats, and U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Systems Integration (page images at HathiTrust)
• FRAP-T5 uncertainty study of five reactor transient and accident events (The Division : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ;, 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)
• Gravity dominated two-phase flow in vertical rod-bundles (The Commission :, 1980), by B. Singh, P. Griffith, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Massachusetts Institute of Technology (page images at HathiTrust)
• Precharacterization report for instrumented fuel assembly (IFA)-527 (Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission :, 1981), by M. E. Cunningham, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation, and Pacific Northwest Laboratory (page images at HathiTrust)
• PBF severe fuel damage scoping test : test results report (Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986), by Alan D. Knipe, Daniel J. Osetek, Scott A. Ploger, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation, and EG & G Idaho (page images at HathiTrust)
• An assessment of LWR fuel-failure propagation potential : literature survey (Division of Systems Safety, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission :, 1980), by August W. Cronenberg, J. H. Scott, U.S. Nuclear Regulatory Commission. Division of Systems Safety, and Los Alamos Scientific Laboratory (page images at HathiTrust)
• Droplet distributions in open pipes and simulated rod bundles (The Commission, 1981), by R. V. Smith, R. D. Lindsted, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation, and Wichita State University. Department of Mechanical Engineering (page images at HathiTrust)
• Pulsed eddy current instrument for measuring sodium levels of EBR-II fuel rods (Argonne National Laboratory, 1961), by Kunio Ono, W. J. McGonnagle, Argonne National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Irradiations of U-20Pu-10Fs alloy fuel rods (Argonne National Laboratory, 1965), by W. N. Beck, R. J. Fousek, J. H. Kittel, Argonne National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Layer formation by interdiffusion between some reactor construction metals (U.S. Atomic Energy Commission, 1955), by J. Howard Kittel, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
• Examination of irradiated experimental NRU fuel rods (Argonne National Laboratory, 1959), by S. H. Paine, W. F. Murphy, U.S. Atomic Energy Comission, and Argonne National Laboratory. Metallurgy Division (page images at HathiTrust)
• Examination of uranium-2 w/o zirconium experimental fuel slugs irradiated in EBR-I (Argonne National Laboratory, 1962), by W. F. Murphy, S. H. Paine, A. C. Klank, U.S. Atomic Energy Comission, and Argonne National Laboratory. Metallurgy Division (page images at HathiTrust)
• Analytic solution of the steady-state wave equation in three dimensions and in irregularly shaped domains with an application to a reactor with partially inserted control rods (Argonne National Laboratory, 1959), by E. J. Betinis, U.S. Atomic Energy Comission, and Argonne National Laboratory (page images at HathiTrust)
• Examination of irradiated RaLa source fuel rod (prototype no. 2) for Los Alamos Scientific Laboratory (Argonne National Laboratory, 1963), by S. H. Paine, F. L. Brown, W. F. Murphy, U.S. Atomic Energy Comission, and Argonne National Laboratory. Metallurgy Division (page images at HathiTrust)
• Examination of uranium from the first core of the Experimental Breeder Reactor I (Argonne National Laboratory, 1961), by W. F. Murphy, S. H. Paine, A. C. Klank, U.S. Atomic Energy Commission, and Argonne National Laboratory. Metallurgy Division (page images at HathiTrust)
• Physics analysis of proposals for Experimental Boiling Water Reactor core 2 (Argonne National Laboratory, 1961), by R. Avery, C. N. Kelber, U.S. Atomic Energy Commission, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust)
• Experimental Boiling Water Reactor core 1A physics analyses (Argonne National Laboratory, 1961), by C. Kelber, H. Iskenderian, C. Carson, K. Almenas, R. Avery, U.S. Atomic Energy Commission, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust)
• The manufacture of supplemental depleted fuel rods for Fuel Cycle Facility startup (Argonne National Laboratory, 1963), by N. J. Jr Carson, A. B. Shuck, H. F. Jelinek, U.S. Atomic Energy Commission, and Argonne National Laboratory. Metallurgy Division (page images at HathiTrust)
• A retrospective analysis of aspects of the ALPR (SL-1) design (Argonne National Laboratory, 1962), by W. J. Kann, D. H. Shaftman, Argonne National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Department of Energy's hanford spent nuclear fuel project : hearing before the Subcommittee on Oversight and Investigations of the Committee on Commerce, House of Representatives, One Hundred Fifth Congress, second session, May 12, 1998. (U.S. G.P.O. :, 1998), by United States House Committee on Commerce, Subcommittee on Oversight and Investigations (page images at HathiTrust)
• Erosion resistance of swaged UO2 following an in-reactor fuel rod cladding failure (Hanford Atomic Products Operation, 1961), by M. K. Millhollen, J. L. Bates, G. R. Horn, U.S. Atomic Energy Commission, Hanford Atomic Products Operation, and Pacific Northwest Laboratory (page images at HathiTrust)
• Boiling burnout experiments with 19-rod bundles in axial flow (U.S. Atomic Energy Commission, 1963), by J. M. Batch, D. E. Fitzsimmons, G. M. Hesson, E. D. Waters, 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 Laboratory (page images at HathiTrust)
• Ultrasonic grain size testing of Hanford fuel elements (U.S. Atomic Energy Commission, 1960), by C. L. Frederick, 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. Engineering Operation (page images at HathiTrust)
• A chart of neutron blackness for soild cylindrical rods (Hanford Atomic Products Operation, 1954), by G. W. Stuart, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
• Quantitative determination of rolling and recrystallization textures in 600°C- and 300°C-rolled uranium rods (Lemont, Illinois : Argonne National Laboratory, 1951., 1951), by Warren P. Chernock, Paul A. Beck, United States. National Technical Information Service, Argonne National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Control rod theory for a cylindrical reactor (U.S. Atomic Energy Commission, Technical Information Service, 1955), by H. L. Garabedian, Westinghouse Electric Corporation. Atomic Power Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Effect of varying reduction on the preferred orientation in rolled uranium rods (United States Atomic Energy Commission, Technical Information Extension ;, 1955), by M. H. Mueller, P. A. Beck, H. W. Knott, Argonne National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• A measurement of neutron temperature in a uranium rod-water moderated lattice (United States Atomic Energy Commission, Technical Information Service, 1955), by Herbert J. C. Kouts, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
• Intracell flux traverses and thermal utilizations for 1.15% enriched uranium rods in ordinary water (United States Atomic Energy Commission, Technical Information Service, 1955), by Herbert J. C. Kouts, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
• Intracell flux traverses and thermal utilizations, 1.027% enrichment uranium rods in light water (United States Atomic Energy Commission, Technical Information Service, 1955), by Herbert J. C. Kouts, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
• A survey of the reflector savings of uranium-water lattices (United States Atomic Energy Commission, Technical Information Service, 1955), by J. Chernick, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
• Intracell flux traverses (United States Atomic Energy Commission, Technical Information Service, 1955), by Herbert J. Kouts, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
• Metallurgy Division. (Oak Ridge National Laboratory, 1957), by R. J. Beaver, C. F. Leitten, R. C. Waugh, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Effect of varying reduction on the preferred orientation in rolled uranium rods (Argonne National Laboratory, 1954), by M. H. Mueller, P. A. Beck, H. W. Knott, Argonne National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Mechanical properties of rolled uranium rods (Argonne National Laboratory, 1956), by R. M. Mayfield, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
• Metals and Ceramics Division. (Oak Ridge National Laboratory, 1968), by A. L. Lotts, F. J. Homan, T. N. Washburn, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Reactor physics of Teapot. Part II (U.S. Atomic Energy Commission, Technical Information Extension ;, 1955), by Paul R. Kasten, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory (page images at HathiTrust)
• Thorium rod blanket study for thermal breeder reactor (United States Atomic Energy Commission, Technical Information Service Extension ;, 1957), by H. C. McCurdy, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Liquid metal fuel reactor experiment : liquid metal control rod corrosion tests (Office of Technical Services, 1959), by W. R. Foley, U.S. Atomic Energy Commission, and Babcock & Wilcox Company (page images at HathiTrust)
• Spectral shift control reactor basic physics program: critical experiments on lattices moderated by D₂O-H₂O mixtures (Office of Technical Services., 1961), by T. C. Engelder, U.S. Atomic Energy Commission, and Babcock & Wilcox Company (page images at HathiTrust)
• Spectral shift control reactor basic physics program : measurement and analysis of uniform lattices of slightly enriched UO₂ moderated by D₂O-H₂O mixtures (Office of Technical Services., 1963), by T. C. Engelder, Babcock & Wilcox Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Spectral shift control reactor basic physics program : measurement and analysis of perturbed lattices of slightly enriched UO₂ moderated by D₂O-H₂O mixtures (Office of Technical Services., 1963), by T. C. Engelder, Babcock & Wilcox Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Spectral shift control reactor basic physics program : measurement of k [infinity] and other lattice parameters by the small lattice experiment technique (Office of Technical Services., 1963), by T. C. Engelder, Babcock & Wilcox Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Development of methods for sealing ends of PWR fuel rods (U.S. Atomic Energy Commission, Technical Information Service Extension, 1957), by J. J. Vagi, D. C. Martin, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• An analysis of transients in a pressurized-water reactor during continuous rod withdrawal (Battelle Memorial Institute, 1956), by Robert F. Redmond, Joel W. Chastain, Joseph J. Stone, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Fabrication of UO₂ fuel rods by vibrational compaction and pressure bonding (Battelle Memorial Institute ;, 1963), by Stanley W. Porembka, Joseph J. Hauth, Charles B. Boyer, 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 (Battelle Memorial Institute ;, 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)
• Forced-flow boiling in rod bundles at high pressure (E.I. du Pont de Nemours & Company, Savannah River Laboratory, 1963), by Bruce Matzner, John S. Neill, U.S. Atomic Energy Commission, Savannah River Laboratory, E.I. du Pont de Nemours & Company, and Columbia University. Heat Transfer Research Facility (page images at HathiTrust)
• Measurements of bucklings and void effects in D₂O-moderated, organic- or H₂O-cooled lattices of UO₂ rod clusters (E.I. du Pont de Nemours & Company, Savannah River Laboratory, 1964), by Frederick D. Benton, A. E. Dunklee, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• The fabrication of the fuel elements for the UO² high burn-up program (United States Atomic Energy Commission, Technical Information Service ;, 1959), by E. A. Lees, R. N. Duncan, M. E. Snyder, General Electric Company, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Preparation of self bonded borides (United States Atomic Energy Commission, Division of Technical Information ;, 1960), by Earl W. Hoyt, Vallecitos Atomic Laboratory, General Electric Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• A survey of new cadmium materials for possible reactor application (United States Atomic Energy Commission, Office of Technical Information ;, 1960), by S. Siegel, General Electric Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Intercomparison measurements (United States Atomic Energy Commission, Office of Technical Information ;, 1961), by William C. Ballowe, John L. Russell, Walter R. Morgan, U.S. Atomic Energy Commission, and General Electric Company (page images at HathiTrust)
• Powder fuel processing by two-pass swaging : the effect of particle size and distribution (U.S. Atomic Energy Commission, Division of Technical Information, 1962), by C. M. Ryer, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Burnout conditions for single rod in annular geometry, water at 600 to 1400 PSIA (U.S. Atomic Energy Commission, Division of Technical Information, 1963), by E. Janssen, J. A. Kervinen, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Fabrication of fuel elements by swaging (United States Atomic Energy Commission, Division of Technical Information, 1962), by E. A. Lees, General Electric Company, 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 (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)
• An experimental parametric study of the effects of control rods on the prompt neutron decay constant in multiplying media (USAEC Division of Technical Information Extension, 1962), by P. Meyer, W. C. Ballowe, U.S. Atomic Energy Commission, General Electric Company, and Vallecitos Atomic Laboratory (page images at HathiTrust)
• Vibration of fuel rods in parallel flow (U.S. Atomic Energy Commission, Division of Technical Information, 1962), by E. P. Quinn, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• UO₂ swaged powder fuel rod failures at high thermal performance conditions (U.S. Atomic Energy Commission, Division of Technical Information, 1963), by T. J. Pashos, B. Weidenbaum, R. C. Nelson, M. F. Lyons, General Electric Company. Atomic Power Equipment Department, U.S. Atomic Energy Commission, and Joint U.S.-Euratom Research and Development Program (page images at HathiTrust)
• Design and fabrication of fuel rods containing low temperature sintered pellets (U.S. Atomic Energy Commission, Division of Technical Information, 1963), by C. J. Baroch, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (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)
• Control rod theories evaluation based upon measurements of control rod worths in SM-I-2 reactor assemblies (General Electric, Aircraft Nuclear Propulsion Dept., 1960), by J. W. Zwick, General Electric Company. Aircraft Nuclear Propulsion Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Development and evaluation of B₄C-graphite control-rod materials for the HTGR (General Atomic Division of General Dynamics Corporation ;, 1962), by W. V. Goeddel, U.S. Atomic Energy Commission, and General Dynamics Corporation. General Atomic Division (page images at HathiTrust; US access only)
• MTR rods as fission product sources for industrial sterilization : engineering feasibility study and cost estimate. Job 24 (Vitro Corporation of America ;, 1954), by General Dynamics Corporation. General Atomic Division, Kellex Corporation, Vitro Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Fission product separation study : quarterly progress report September 27-November 30, 1956, Job 2077 (Vitro Laborartories ;, 1956), by General Dynamics Corporation. General Atomic Division, Kellex Corporation, Vitro Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Irradiation test of gadolinium and samarium oxides for the Hallam Nuclear Power Facility control rod program (Canoga Park, Calif. : Atomics International, 1962., 1962), by T. E. Redding, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Control rod calibrations for the Sodium Reactor Experiment with thorium-uranium fuel (Atomics International, 1962), by R. W. Keaten, R. A. Lewis, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Fuel rod bowing in the Sodium Reactor Experiment (Atomics International, 1962), by H. F. Donohue, R. W. Keaten, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Resonance escape probability of a lattice of multi-rod fuel elements (Atomics International, 1959), by C. H. Skeen, W. W. Brown, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Hydraulic characteristics of Hallam Nuclear Power Facility 8-rod fuel element (Canoga Park, California : Atomics International, 1963., 1963), by R. J. Begley, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Detecting and eliminating fuel rod bowing in the Sodium Reactor Experiment (Canoga Park, California : Atomics International, 1963., 1963), by R. W. Woodruff, R. W. Keaten, C. W. Griffin, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Development of the Sodium Reactor Experiment Mark II safety rod (Atomics International, 1959), by E. C. Phillips, R. G. Hoff, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Magnetic pulse swaging of Aluminum Powder Metallurgy-UOb2s fuel rods (Canoga Park, California : Atomics International, 1963., 1963), by E. C. Supan, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Measurement of the Sodium Reactor Experiment power coefficients and reactor parameters utilizing the oscillation techniques (Atomics International, 1960), by C. W. Griffin, J. G. Lundholm, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Statistical treatment of hot channel factors for compact reactors (Canoga Park, California : Atomics International, 1963., 1963), by P. D. Cohn, H. A. Evans, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Nondestructive determination of uranium-235 content of Systems Nuclear Auxiliary Power fuel rods : volume II statistical methods for evaluating data obtained from counting experiments (Canoga Park, California : Atomics International, 1964., 1964), by M. A. Greenfield, R. L. Koontz, C. T. Nelson, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
• Nondestructive determination of Up235s content of Systems Nuclear Auxiliary Power fuel rods : vol. III - equipment description and production quality control applications (Canoga Park, California : Atomics International, 1965., 1965), by A. R. Mooers, R. C. Barry, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
• Buckling of graphite moderated lattices containing seven rod fuel clusters (Atomics International, 1956), by F. L. Fillmore, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
• Reactivity worths of several fast reactor control materials (Atomics International, 1965), by R. W. Campbell, S. G. Carpenter, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Development of the Sodium Reactor Experiment Mark I safety rod (Atomics International, 1959), by E. C. Phillips, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
• Development of the Sodium Reactor Experiment thimble-type control rods, Mark I and II (Atomics International, 1959), by A. E. Miller, U.S. Atomic Energy Commission. Technical Information Center, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Melting and forming of SNAP Experimental Reactor fuel rods (Atomics International, 1960), by P. S. Drennan, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Flux hardening in fuel rods (Atomics International, 1960), by E. U. Vaughan, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Isostatic pressing of UO₂ in high temperature metals (Oak Ridge, Tennessee : Technical Infromation Service ; Washington, D.C. : Office of Technical Services, Department of Commerce, 1960., 1960), by I. Sheinhartz, J. Fugardi, Sylvania-Corning Nuclear Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Measurements of thermal utilization, resonance escape probability, and fast fission factor of water moderated slightly enriched uranium lattices (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service ; [Washington, D.C.] : [Available from the Office of Technical Services, Dept. of Commerce], [1956], 1956), by A. Z. Kranz, Bettis Atomic Power Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Kinetic and buckling measurements on lattices of slightly enriched uranium or UO₂ rods in light water (Pittsburgh, Pennsylvania. : Bettis Plant, 1958., 1958), by J. R. Brown, B. H. Noordhoff, J. C. Andrews, J. J. Volpe, F. S. Frantz, D. R. Harris, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Development and properties of silver-base alloys as control rod materials for pressurized water reactors (Pittsburgh, Pennsylvania : Bettis Atomic Power Laboratory, 1959., 1959), by I. Cohen, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• A theoretical method for determining the worth of control rods (Pittsburgh, Pennsylvania : Bettis Plant, 1959., 1959), by A. F. Henry, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Isotopic content of irradiated natural uranium dioxide fuel rods PWR Core 1 (Washington, D.C. : Office of Technical Services, Department of Commerce, 1962., 1962), by C. D. Sphar, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• The properties of hafnium from a PWR Core 1 control rod after one seed life exposure (Washington, D.C. : Office of Technical Services, Department of Commerce, 1962., 1962), by G. J. Salvaggio, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Properties of a hafnium control rod after exposure during two seed lives in pwr core 1 (Washington, D.C. : Office of Technical Services, Department of Commerce, 1962., 1962), by G. J. Salvaggio, J.P. Bacca, F.A. Nichols, Bettis Atomic Power Laboratory, Westinghouse Electric Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Properties of a hafnium control rod after exposure during three seed lives in PWR Core 1 (Washington, D.C. : Office of Technical Services, Department of Commerce, 1965., 1965), by G. J. Salvaggio, K.J. Longua, S. Kass, J.G. Weinberg, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Yankee Atomic Electric Company, research and development program (Pittsburgh, Pennsylvania : Westinghouse Electric Corporation, Atomic Power Department, 1959., 1959), by William H. Arnold, Yankee Atomic Electric Company, Westinghouse Electric Corporation. Atomic Power Division, and U.S. Atomic Energy Commission. Technical Information Service Extension (page images at HathiTrust)
• Multi-region reactor lattice studies (Pittsburgh, Pennsylvania : Westinghouse Electric Corporation, Atomic Power Department, 1960., 1960), by V. E. Grob, J. D. Cleary, F. L. Kelly, R. D. Leamer, D. F. Hanlen, P. W. Davison, Westinghouse Electric Corporation. Atomic Power Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Multi-region reactor lattice studies : microscopic lattice parameters in single-and multi-region cores : a comparison of theory and experiment (Pittsburgh, Pennsylvania : Westinghouse Electric Corporation, Atomic Power Department, 1961., 1961), by P. W. Davison, G. H. Minton, H. A. Risti, B. Jennings, J. D. Cleary, Westinghouse Electric Corporation. Atomic Power Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Power density and burnup distributions in Yankee Core I (Pittsburgh, Pennsylvania : Westinghouse Electric Corporation, Atomic Power Division, 1963., 1963), by J. D. McGaugh, R. H. Chastain, Westinghouse Electric Corporation. Atomic Power Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Casting of uranium rods at Iowa State College (Ames, Iowa : Institute for Atomic Research ; Oak Ridge, Tenn. : Technical Information Service, 1945., 1945), by Harley A. Wilhelm, U.S. Atomic Energy Commission. Technical Information Service Extension, and Iowa State College (page images at HathiTrust)
• Fission product separation study : quarterly progress report December 1, 1956 - February 28, 1957, Job 2077. (Vitro Laborartories, 1957), by Union Carbide Nuclear Company, Vitro Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Control rod evaluation by means of perturbation theory (Canoga Park, California : Atomics International, [1956], 1956), by F. L. Fillmore, U.S. Atomic Energy Commission, and North American Aviation. Atomics International Division (page images at HathiTrust)
• Absorption of neutrons by black control rods (Knolls Atomic Power Laboratory, General Electric Company, 1955), by H. Hurwitz, G. M. Roe, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• Interaction of black control rods (Knolls Atomic Power Laboratory, General Electric Company, 1956), by J. C. Stewart, J. H. Smith, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• RODCOST : a program for calculating the cost of fabricating UOb2 sand PuOb2s-UOb2 fuel rods as a function of design (Richland, Washington : Pacific Northwest Laboratory, 1968., 1968), by G. L. Simmons, J. B. Burnham, B. M. Cole, Battelle Memorial Institute. Pacific Northwest Division, U.S. Atomic Energy Commission, and Pacific Northwest Laboratory (page images at HathiTrust)
• In-pile measurement of the thermal conductivity of irradiated metallic fuel (Argonne, Illinois : Argonne National Laboratory, Reactor Engineering Division, 1993., 1993), by T. H. Bauer, J. W. Holland, University of Chicago, and Argonne National Laboratory (page images at HathiTrust)
• Description of a pilot-scale facility for uranium dioxide-plutonium dioxide processing studies (Argonne National Laboratory, 1964), by G. J. Vogel, W. J. Mecham, E. L. Carls, and Argonne National Laboratory. Chemical Engineering Division (page images at HathiTrust)
• Fabrication of fuel rods by tandem rolling (United States Atomic Energy Commission, Office of Technical Information ;, 1961), by J. W. Lingafelter, U.S. Atomic Energy Commission, and General Electric Company (page images at HathiTrust)
• Evaluation of failed hot gas isostatic pressed fuel rods (U.S. Atomic Energy Commission, Division of Technical Information, 1963), by C. J. Baroch, C. B. Boyer, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Multi-rod burnout at high pressure (U.S. Atomic Energy Commission, Division of Technical Information, 1962), by E. E. Polomik, E. P. Quinn, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Behavior of defective PWR fuel rods during power ramp and film boiling operation (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1979., 1979), by Douglas W. Croucher, Idaho National Engineering Laboratory, EG & G Idaho, United States. Department of Energy. Idaho Operations Office, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• ANS54, a computer subroutine for predicting fission gas release (Washington, D.C. : Core Performance Branch, Division of Systems Safety, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1980., 1980), by W. N. Rausch, F. E. Panisko, Pacific Northwest Laboratory, U.S. Nuclear Regulatory Commission. Division of Systems Safety. Core Performance Branch, United States Government Printing Office, and United States. National Technical Information Service (page images at HathiTrust)
• Description and characterization of evaluation models in FRAPCON-1 (Washington, D.C. : Division of Systems Integration, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1980., 1980), by E. T. Laats, R. Chambers, United States. National Technical Information Service, United States Government Printing Office, and U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Systems Integration (page images at HathiTrust)
• Evaluation of power reactor fuel rod analysis capabilities : phase 1 topical report (Washington, D.C. : Division of Reactor Safety Research, 1983., 1983), by Dennis R. Coleman, D. L. Harrison, Control Data Corporation. Utility Associates International, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• Crossflow mixing between parallel flow channels during boiling : Part III, Effect of spacers on mixing between two channels (Richland, Washington : Reactor Engineering Department, Physics and Engineering Division, Pacific Northwest Laboratory, 1969., 1969), by D. S. Rowe, C. W. Angle, U.S. Atomic Energy Commission, and Pacific Northwest Laboratory (page images at HathiTrust)
• Irradiation performance of Piqua Core I fuel elements (Downey, California : North American Aviation, Inc., Atomics International, 1966., 1966), by J. L. Arnold, North Amercian Aviation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Quarterly technical report : SPERT project, October, November, December, 1967 (Washington, D. C. : National Reactor Testing Station, U.S. Atomic Energy Commission, 1968., 1968), by T. G. Taxelius, J. C. Haire, S. G. Forbes, Phillips Petroleum Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Reactivity accident test results and analyses for the SPERT III e-core -- a small, oxide-fueled, pressurized-water reactor (Washington, D. C. : National Reactor Testing Station, U.S. Atomic Energy Commission, 1969., 1969), by R. K. McCardell, J. E. Houghtaling, D. I. Herborn, Phillips Petrolium Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Quarterly technical report : SPERT project, January, February, March 1968 (Washington, D. C. : National Reactor Testing Station, U.S. Atomic Energy Commission, 1968., 1968), by T. G. Taxelius, J. C. Haire, S. G. Forbes, Phillips Petroleum Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Quarterly technical report : SPERT project, April, May, June1968 (Washington, D. C. : National Reactor Testing Station, U.S. Atomic Energy Commission, 1969., 1969), by T. G. Taxelius, J. C. Haire, S. G. Forbes, Phillips Petroleum Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Fuel rod deformation in the SPERT III oxide e-core (Washington, D. C. : National Reactor Testing Station, U.S. Atomic Energy Commission, 1969., 1969), by W. H. Etz, Phillips Petrolium Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Quarterly technical report : SPERT project, July, August, September 1968 (Washington, D. C. : National Reactor Testing Station, U.S. Atomic Energy Commission, 1969., 1969), by T. G. Taxelius, S. O. Johnson, S. G. Forbes, Phillips Petroleum Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• A Monte Carlo calculation of thermal utilization (New York, New York : AEC Computing and Applied Mathematics Center, Institute of Mathematical Sciences, New York University, 1958., 1958), by A. Rotenberg, Robert D. Richtmyer, A. Lapidus, New York University. Institute of Mathematical Sciences, and U.S. Atomic Energy Commission. New York Operations Office (page images at HathiTrust)
• SNAP 8 development reactor nuclear analysis ([Canoga Park, California] : Atomics International, North American Rockwell, 1969., 1969), by L. D. Swenson, U.S. Atomic Energy Commission, and Rockwell International. Atomics International Division (page images at HathiTrust)
• Inspection of the rods in JEEP during the period December 1 - 7, 1952 (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service, 1953., 1953), by J. Brun, Joint Establishment for Nuclear Energy Research (Netherlands and Norway), and U.S. Atomic Energy Commission (page images at HathiTrust)
• Feasibility report for casting and extruding uranium-thorium fuel rods for Atomics International (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1957., 1957), by W. L. Larson, North American Aviation. Atomics International Division, Inc Nuclear Metals, and U.S. Atomic Energy Commission (page images at HathiTrust)

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