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Nuclear reactors -- Cores -- Computer programs

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• Nuclear reactors -- Cores
• Nuclear reactors -- Computer programs

• Nuclear reactors -- Cores -- Mathematical models -- Computer programs

• Program for interpreting program 18-0 source and escape particle tapes (General Electric Company, Nuclear Materials and Propulsion Operation, 1962), by J. P. Yalch, J. E. MacDonald, General Electric Company. Nuclear Materials and Propulsion Operation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Calculation of cross-section space shielding factors for doubly heterogeneous reactor cores : pointwise or ultrafine group method (Los Alamos, New Mexico : Los Alamos Scientific Laboratory of the University of California, [1977], 1977), by M. G. Stamatelatos, R. J. LaBauve, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, and Los Alamos Scientific Laboratory (page images at HathiTrust)

• PROP and JET : a program for the synthesis and survey of three-dimensional power shapes on the IBM-704 (Washington, D.C. : Office of Technical Services, Department of Commerce, 1958., 1958), by J. G. Fairey, R. B. Smith, A.V. Pace, S.H. Meanor, Callaghan,J.B., J.E. Meyer, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)

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

• Physical and metallurgical changes in the core. (Argonne National Laboratory, 1957), by J. H. Kittel, R. F. Buchanan, and M. Novick (page images at HathiTrust)
• Nondestructive tests of components of EBR-I, CORE IV (Argonne National Laboratory, 1963), by K. Balaramamoorthy, R. B. Perry, C. J. Renken, R. H. Slener, India Atomic Energy Establishment. Bombay 1, and Argonne National Laboratory. Metallurgy Division (page images at HathiTrust)
• Some considerations on the meltdown problem for Fast Reactor Test (Argonne National Laboratory, 1964), by B. Warman, S. Grifoni, U. Wolff, A. Watanabe, P. J. Persiani, and Argonne National Laboratory. Reactor Physics Division (page images at HathiTrust)
• Flux trap experiments in D2O-moderated thoria-urania cores (Argonne National Laboratory, 1964), by K. E. Plumlee and Argonne National Laboratory. Reactor Physics Division (page images at HathiTrust)
• A zoned loading for a Zero Power Reactor III type facility (Argonne National Laboratory, 1964), by A. G. Edwards and Argonne National Laboratory. Idaho 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, 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, 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, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust)
• Experiments with central superheater core CSH-1, Boiling Reactor Experiment V (Argonne National Laboratory, 1965), by Argonne National Laboratory) BORAX-V Project Staff (Idaho Division and Argonne National Laboratory. Idaho Division (page images at HathiTrust)
• Lecture notes on in-core instrumentation for the measurement of hydrodynamic parameters in water-cooled reactors (Argonne National Laboratory, 1961), by Glenn F. Popper and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust)
• Feasibility of Pu239-U235-fueled cores to predict Pu239-fueled core dimensions (Argonne National Laboratory, 1962), by D. Meneghetti, H. Ishikawa, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust)
• Some calculations for a plutonium-fueled Zero Power Reactor III (Argonne National Laboratory, 1960), by A. R. Baker and Argonne National Laboratory. Idaho Division (page images at HathiTrust)
• Inspection of fuel element components and fuel elements for the Argonne low power reactor (Argonne National Laboratory, 1959), by W. J. McGonnagle, N. P. Lapinski, and W. N. Beck (page images at HathiTrust)
• Some calculations pertaining to fast reactor safety (Argonne National Laboratory, Reactor Engineering Division, 1962), by D. M. O'Shea, J. M. Chaumont, D. Okrent, and Argonne National Laboratory (page images at HathiTrust)
• The fabrication of certain jacketed uranium helices (Argonne National Laboratory, 1957), by F. L. Yaggee (page images at HathiTrust)
• Preliminary results of high-temperature bare U²³⁵-C critical assembly measurements (Lawrence Radiation Laboratory, 1961), by Reinald G. Finke and Lawrence Radiation 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, Hanford Works, and Hanford Atomic Products Operation. Reactor and Fuels Laboratory (page images at HathiTrust)
• Lattice parameter measurements for a concentric tube fuel element (U.S. Atomic Energy Commission, 1960), by D. E. Wood, E. Z. Block, K. R. Birney, Hanford Works, and Hanford Atomic Products Operation. Hanford Laboratories Operation (page images at HathiTrust)
• A data recording system for the fuel core tester (U.S. Atomic Energy Commission, 1960), by G. L. Waldkoetter, Hanford Works, and Hanford Atomic Products Operation. Engineering Operation (page images at HathiTrust)
• Ultrasonic grain size testing of Hanford fuel elements (U.S. Atomic Energy Commission, 1960), by C. L. Frederick, Hanford Works, and Hanford Atomic Products Operation. Engineering Operation (page images at HathiTrust)
• Material buckling measurements on graphite-uranium systems at Hanford : a summary tabulation (U.S. Atomic Energy Commission, 1961), by D. E. Wood, Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust)
• Measurement of negative kex for a graphite uranium lattice in the PCTR (U.S. Atomic Energy Commission, 1960), by E. Z. Block, D. E. Wood, Hanford Works, and Hanford Atomic Products Operation. Physics and Instrument Research and Development Operation (page images at HathiTrust)
• Two-group, small source theory applied to an infinite array of reactor super-lattices (U.S. Atomic Energy Commission, 1960), by J. R. Worden, Hanford Works, and Hanford Atomic Products Operation. Physics and Instrument Research and Development Operation (page images at HathiTrust)
• Thermal utilization, thermal flux, and lattice cell shape (U.S. Atomic Energy Commission, 1957), by H. Neumann, Hanford Works, and Hanford Atomic Products Operation. Physics and Instrument Research and Development Operation (page images at HathiTrust)
• Pile perturbation theory (Atomic Energy Commission, 1946), by H. Soodak and U.S. Atomic Energy Commission (page images at HathiTrust)
• Temperature distribution in flat plate with exponential heat source (Oak Ridge National Laboratory, 1956), by F. T. Binford, M. L. Nelson, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory (page images at HathiTrust)
• Low-power criticality experiments on the homogeneous reactor experiement (HRE-1) (Oak Ridge National Laboratory, 1957), by Sidney Visner, Phillip M. Wood, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory. Reactor Experimental Engineering Division (page images at HathiTrust)
• Comparison of pool-type reactor critical experiments with two-group and thirty-group calculations (Oak Ridge National Laboratory, 1958), by Ernest Gerard Silver, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Applied Nuclear Physics Division (page images at HathiTrust)
• The reactivity effect of an air tank against one face of the bulk shielding reactor (Oak Ridge National Laboratory, 1957), by E. B. Johnson, J. D. Flynn, K. M. Henry, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory. Applied Nuclear Physics Division (page images at HathiTrust)
• A study of the nuclear and physical properties of the ORNL graphite reactor shield (Oak Ridge National Laboratory, 1958), by M. A. Welt, D. W. Vroom, T. O. P. Speidel, A. B. Reynolds, R. C. Reid, J. F. Nichols, D. T. Morgan, L. A. Lee, G. W. Bond, T. V. Blosser, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory. Neutron Physics Division (page images at HathiTrust)
• CRUD : a fission-product diffusion code for the CDC 3600 and IBM 7094 (Lawrence Radiation Laboratory, 1964), by G. M. Litton, C. R. Hunt, United States. National Bureau of Standards. Fracture and Deformation Division, and Lawrence Radiation Laboratory (page images at HathiTrust)
• Reactor stability in the Spert IV facility (U.S. Atomic Energy Commission, Idaho Operations Office, 1965), by L. A. Stephan, R. M. Potenza, Zoel R. Martinson, J. G. Crocker, U.S. Atomic Energy Commission. Idaho Operations Office, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Metallurgical examination of a melted SPERT-I type-B fuel plate (U.S. Atomic Energy Commission, Idaho Operations Office, 1958), by W. O. Schaffnit and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Report of the SPERT I destructive test program on an aluminium, plate-type, water-moderated reactor (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by R. W. Miller, Alain Sola, R. K. McCardell, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Transient temperature distributions in the SPERT I D-12/25 fuel plates during short-period power excursions (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by J. E. Houghtaling, Alain Sola, A. H. Spano, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Fuel plate experience during the SPERT I destructive test series with an aluminum-clad, plate-type core (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by J. Dugone, D. D. Wieland, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Non-destructive and destructive transient tests of the SPERT I-D, fully-enriched, aluminum-plate-type core : data summary report (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by M. R. Zeissler, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Self-limiting excursion tests of a highly enriched plate-type D₂O-moderated reactor. Part I, Initial test series (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by J. E. Grund, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Nuclear start-up of the SPERT IV reactor (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by J. G. Crocker, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• SPERT I low-enrichment oxide core destructive test program safety analysis report (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by J. E. Grund, B. E. Norton, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Summary data report for SPERT transient pressure measurements in the interval 1955 to 1961 (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by G. F. Brockett, E. Feinauer, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Self-limiting excursion tests of a highly enriched plate-type D₂O-moderated reactor. Part III, Effect of system temperature (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by R. C. Schmitt, J. E. Grund, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Self-limiting excursion tests of the SPERT II highly enriched plate-type D₂O-moderated reactor. Part IV, Data summary report (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by V. W. Goldsberry, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Critical loading and initial static experiments in the SPERT II reactor with a close-packed D₂O-moderated core (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by J. A. McClure, R. L. Johnson, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Reactor power excursion tests in the SPERT IV facility (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by J. G. Crocker, L. A. Stephan, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Transient tests of the fully enriched, stainless steel plate-type, P core in the Spert I reactor : data summary report (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by A. P. Wing, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Fuel plate resistance thermometer (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by R. H. Meservey, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Transient tests of the fully enriched, aluminum plate-type, B cores in the Spert I reactor : data summary report (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by A. P. Wing, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Self-limiting excursion tests of a highly enriched plate-type D₂O-moderated reactor. Part II, Effect of system pressure (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by R. L. Johnson, J. E. Grund, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Experimental results of potentially destructive reactivity additions to an oxide core (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by J. E. Barry, J. E. Grund, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Engineering test reactor core hydraulics (U.S. Atomic Energy Commission, Idaho Operations Office, 1958), by R. G. Beck, J. H. Rainwater, E. S. Brown, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Preliminary evaluation of the 20% enriched uranium core for the Materials Testing Reactor (U.S. Atomic Energy Commission, Idaho Operations Office, 1958), by D. R. DeBoisblanc, R. S. Marsden, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Behavior of the Xe concentration in the MTR after a power reduction (U.S. Atomic Energy Commission, Technical Information Service, 1955), by J. W. Webster and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Nuclear aspects of proposed 19-plate fuel assemblies (U.S. Atomic Energy Commission, Technical Information Service Extension, 1952), by G. H. Hanson, H. L. McMurry, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• The age in beryllium--water mixtures (U.S. Atomic Energy Commission, Technical Information Service, 1953), by H. L. McMurry and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Effect on flux of a fuel plate in reflector (U.S. Atomic Energy Commission, Technical Information Service, 1953), by J. W. Webster, H. L. McMurry, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• A proposal for an in-pile film boiling experiments in the MTR (U.S. Atomic Energy Commission, Technical Information Service, 1953), by C. F. Leyse and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Nuclear calculations for SPERT III (U.S. Atomic Energy Commission, Idaho Operations Office, 1957), by H. L. McMurry and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Three and two group constants for a SPERT III core (U.S. Atomic Energy Commission, Idaho Operations Office, 1957), by Dale Robert Metcalf, Robert Haldin, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Nuclear calcualtions for SPERT III zirconium core (U.S. Atomic Energy Commission, Technical Information Service Extension, 1956), by G. A. Cazier, B. L. Hanson, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• A four-region, two-group calculation of SPERT III critical size and flux distribution (U.S. Atomic Energy Commission, Idaho Operations Office, 1957), by Dale Robert Metcalf, V. C. Kobold, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Self-limiting power excursion tests of a water-moderated low-enrichment UO₂ core in SPERT I (U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by A. H. Spano, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Transient tests of the SPERT I low-enrichment UO₂ core : data summary report (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by R. Scott, R. C. Schmitt, A. A. Wasserman, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Stability and transient analysis of the EOCR (U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by S. R. Gossman, F. K. Hyer, K. V. Moore, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Nuclear start-up of the special power excursion reactor tests II reactor with heavy-water moderator (U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by J. E. Grund, R. L. Johnson, T. H. Davis, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Transient tests of the BSR-II core in the SPERT I facility (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by L. A. Stephan, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• SPERT I destructive test program safety analysis report (U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by A. H. Spano, R. W. Miller, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Thermocouple attachment for the initial EOCR core (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by D. R. Conkling, T. L. Rasmussen, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Reactor core thermocouple locations (ECOR initial core) (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by R. G. Young, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Use of "Binal" in reactor control rods (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by R. E. Heffner, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Spent fuel element activity and core burnup distribution from the Materials Testing Reactor plutonium core loading (U.S. Atomic Energy Commission, Idaho Operations Office, 1959), by J. M. Waage and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Core power variation and fuel burnup in the engineering test reactor (U.S. Atomic Energy Commission, Idaho Operations Office, 1959), by L. J. Harrison and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Progress report on fuel element development and associated projects (U.S. Atomic Energy Commission, Idaho Operations Office, 1960), by J. M. Beeston, S. E. Craig, W. C. Francis, 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 (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)
• Operating parameters and neutron flux profiles for MTR plutonium core (U.S. Atomic Energy Commission, Idaho Operations Office, 1959), by L. J. Harrison, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Tory II-A mechanical and aero-thermodynamic design ([Lawrence] Radiation Laboratory, 1962), by J. W. Cox, U.S. Atomic Energy Commision, and Livermore. Lawrence Radiation Laboratory University of California (page images at HathiTrust)
• The LRL advanced reactors studies program a review ([Lawrence] Radiation Laboratory, 1962), by Robert Fox, United States. Department of Energy. Office of Fusion Energy (Office of Fusion Energy), United States. National Bureau of Standards. Facture and Deformation Division, U.S. Atomic Energy Commision, and Livermore. Lawrence Radiation Laboratory University of California (page images at HathiTrust)
• Experimental study of effect of simulated reactor core position on nozzle heat transfer (National Aeronautics and Space Administration ;, 1966), by James F. Schmidt and Lewis Research Center (page images at HathiTrust)
• NASA TN D-4582 (National Aeronautics and Space Administration ;, 1968), by R.M. Williams, W.J. Bifano, Lewis Research Center, and United States National Aeronautics and Space Administration (page images at HathiTrust)
• Uranium-water lattice compilation. Part I, BNL exponential assemblies (Brookhaven National Laboratory, 1966), by Glenn A. Price, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Instrumentation systems to protect LMFBR core integrity (Argonne National Laboratory, 1971), by W. C. Lipinski, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
• Beryllium-reflected, graphite-moderated critical assemblies (Los Alamos Scientific Laboratory of the University of California, 1957), by Hugh Campbell Paxton, John D. Orndoff, J. C. Hoogterp, G. E. Hansen, U.S. Atomic Energy Commission, and Los Alamos Scientific Laboratory (page images at HathiTrust)
• Molten Plutonium Pump Experiment (Los Alamos Scientific Laboratory of the University of California, 1962), by John E. Deverall, G. L. Caldwell, Los Alamos Scientific Laboratory. K- Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Temperature dependent kinetics of coupled-core reactors (Los Alamos Scientific Laboratory of the University of California, 1964), by Curtis G. Chezem, Robert L. Seale, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Pressure drop and gas residence time for a four foot core (United States Atomic Energy Commission, Technical Information Service, 1955), by Leon Cooper, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory (page images at HathiTrust)
• Conversion in a two-region reactor (United States Atomic Energy Commission, Technical Information Service, 1955), by M. Tobias, R. E. Aven, Paul N. Haubenreich, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory (page images at HathiTrust)
• A two-region homogeneous reactor without a core tank (United States Atomic Energy Commission, Technical Information Service ;, 1955), by Sidney Visner, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• ML-1-1A core studies with the Gas cooled reactor experiment critical assembly (Battelle Memorial Institute, 1959), by Joel W. Chastain, David A. Dingee, William S. Hogan, R. A. Egen, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Variable moderator reactor critical-assembly studies (Battelle Memorial Institute ;, 1960), by Joel W. Chastain, David A. Dingee, William S. Hogan, Lee H. Bettenhausen, R. A. Egen, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• ML-1-1B critical assembly studies (Battelle Memorial Institute ;, 1961), by Joel W. Chastain, David A. Dingee, William S. Hogan, Richard G. Matthews, Joseph W. Ray, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Addendum to the SPERT III hazards summary report : low-enrichment oxide core (U.S. Atomic Energy Commission, Idaho Operations Office, 1965), by J. E. Houghtaling, J. C. Haire, J. A. Norbert, Idaho National Reactor Testing Station, U.S. Atomic Energy Commission. Idaho Operations Office, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
• Interim report on Scoping Emergency Cooling Heat Transfer Series I and II (U.S. Atomic Energy Commission, Idaho Operations Office, 1968), by L. G. Schlenker, W. S. Little, C. M. Moser, Idaho National Reactor Testing Station, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
• PARET : a program for the analysis of reactor transients (U.S. Atomic Energy Commission, Idaho Operations Office, 1969), by C. F. Obenchain, Idaho National Reactor Testing Station, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
• Critical mass measurements of Oy and Pu cores in spherical aluminum reflectors (Los Alamos Scientific Laboratory of the University of California, 1961), by D. P. Wood, B. Peña, U.S. Atomic Energy Commission, and Los Alamos Scientific Laboratory (page images at HathiTrust)
• A radiation reactor concept (glowworm) (Los Alamos Scientific Laboratory of the University of California, 1963), by L King, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Critical masses of composites of Oy and Pu-239-240 in flattop geometry (Los Alamos Scientific Laboratory of the University of California, 1961), by D. M. Barton, G. E. Hansen, William Bernard, U.S. Atomic Energy Commission, and Los Alamos Scientific Laboratory (page images at HathiTrust)
• RAC, a computer program for reactor accident calculations (Los Alamos Scientific Laboratory of the University of California, 1963), by Curtis G. Chezem, W. R. Stratton, U.S. Atomic Energy Commission, and Los Alamos Scientific Laboratory (page images at HathiTrust)
• Coupled-core reactors (Los Alamos Scientific Laboratory of the University of California, 1964), by Robert L. Seale, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Investigation of coupled Rover cores (Los Alamos Scientific Laboratory of the University of California, 1964), by Robert L. Seale, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• T7 tanker reactor control system (U.S. Atomic Energy Commission, Division of Technical Information, 1961), by O. A. Thompson, H. A. Brammer, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• In-core power monitoring of nuclear reactors (U.S. Atomic Energy Commission, Division of Technical Information, 1962), by R. A. DuBridge, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• In-core instrumentation development : first topical report. Task II, Phase I, Telemetering (U.S. Atomic Energy Commission, Division of Technical Information, 1962), by A. C. Duckart, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• In-core instrumentation development program (U.S. Atomic Energy Commission, Division of Technical Information, 1963), by R. A. DuBridge, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• In-core instrumentation development program (U.S. Atomic Energy Commission, Division of Technical Information, 1963), by A. H. McQueen, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Nuclear test gage safety experiment (General Electric Company, 1958), by J. N. Renaker, V. J. Stratton, U.S. Atomic Energy Commission, and General Electric Company. Aircraft Nuclear Propulsion Department. Atomic Products Division (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)
• The DASA-TRIGA Mark F pulsing reactor facility (Technical Services, Department of Commerce, 1961), by C.E. Clifford, G. B. West, R.H. Stahl, M. S. Nelkin, U.S. Atomic Energy Commission, and General Dynamics Corporation. General Atomic Division (page images at HathiTrust)
• Tests on half-scale flow model of 40-MW(E) prototype HTGR (Peach Bottom Atomic Power Station) (General Atomic Division of General Dynamics Corporation ;, 1962), by S. Ross, R. A. Skeehan, E. A. Day, General Dynamics Corporation. General Atomic Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Flux peaking near reactor water gaps (Knolls Atomic Power Laboratory, General Electric Company, 1956), by L. S. Ring, J. C. Stewart, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• The space-time neutron kinetics by a variational method with application to power reactor dynamics (Knolls Atomic Power Laboratory, 1962), by D. E. Dougherty, Knolls Atomic Power Laboratory, General Electric Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Sodium Reactor Experiment core recovery program (Atomics International, 1961), by W. J. Freede, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Fabrication of ceramic internal reflector for the SNAP 8 experimental reactor (Atomics International, 1962), by K. Langrod, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Experimental testing of core component handling equipment and handling techniques for Hallam Nuclear Power Facility (Canoga Park, California : Atomics International, 1964., 1964), by W. A. Kaspic, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Predicted nuclear characteristics of the Hallam Nuclear Power Facility first core (Canoga Park, California : Atomics International, 1964., 1964), by M. P. Aronchick, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Evaluation of calandria, thimble, and canned-moderator concepts for sodium graphite reactors (Atomics International, 1960), by G. L. Reed, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Sodium Reactor Experiment third core heat transfer analysis interim report (Canoga Park, California : Atomics International, 1963., 1963), by J. S. McDonald, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• A reactor transient heat transfer model (Canoga Park, California : Atomics International, 1964., 1964), by D. G. Mason, R. W. Winson, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Organic Moderated Reactor Experiment fourth core hazards report (Canoga Park, California : Atomics International, 1963., 1963), by J. D. Gylfe, S. Yee, R. Stanbridge, J. Otter, J. Marvosh, W. W. Davis, J. H. Campo, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Fabrication of uranium alloy fuel elements for Organic Moderated Reactor Experiment fourth core (Atomics International, 1963), by R. M. Crawford, E. E. Garrett, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Mathematical model describing the dynamics of the Sodium Reactor Experiment core II (Canoga Park, California : Atomics International, 1963., 1963), by R. W. Keaten, W. J. Carlson, A. L. Gunby, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Design of a calandria core for the Sodium Reactor Experiment (Atomics International, 1959), by J. B. Williams, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Experiments with water-reflected, undermoderated, zirconium hydride critical assemblies (Canoga Park, California : Atomics International, 1963., 1963), by L. I. Moss, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Nuclear parameters of the Sodium Reactor Experiment core II (Canoga Park, California : Atomics International, 1964., 1964), by R. W. Keaten, A. L. Gunby, R. D. Phelps, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
• Core optimization studies (Canoga Park, California : Atomics International, 1964., 1964), by H. Rood, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
• Measurement of the reactivity absorbed by sodium in the SRE (Canoga Park, California : Atomics International, 1964., 1964), by A. L. Gunby, J. M. Kallfelz, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
• Core II physics tests on the SRE (Canoga Park, California : Atomics International, 1964., 1964), by M. R. Pellet, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
• Two-group calculations of the critical core size of the SRE reactor (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)
• Two-group calculations of the critical core size of the SRE reactor (Atomics International, 1959), by F. L. Fillmore, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
• Preliminary design of a calandria core for the sodium reactor experiment (Atomics International, 1957), by J. E. Mahlmeister, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
• Reflector control of OMR (United States Atomic Energy Commission, Technical Information Service, 1957), by W. W. Davis, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
• Core parameter survey report for organic cooled reactors (Atomics International, 1959), by R. W. Hardy, B. L. Hoffman, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Evaluation of flux flattening in sodium graphite reactor cores (Atomics International, 1960), by Roy Arthur Axford, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• PM-1 critical experiments and zero power testing (United States Atomic Energy Commission, Division of Technical Information ;, 1961), by H. L. Vener, J. F. O'Brien, Martin Company. Nuclear Division, and U.S. Atomic Energy Commission. Division of Reactor Development (page images at HathiTrust)
• Experimental and theoretical study of critical slabs : effect of absorbing membranes of cadmium, gold, and boron (Pittsburgh, Pennsylvania : Bettis Plant, 1957., 1957), by A. D. Voorhis, D. R. Connors, R. T. Jones, M. Goldsmith, Terence M. Ryan, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• The sampling estimate of the parameter variance/mean in reactor fluctuation measurements (Washington, D.C. : Office of Technical Services, Department of Commerce, 1958., 1958), by D. B. Harris, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Neutron bursts in a ring reactor (Washington, D.C. : Office of Technical Services, Department of Commerce, 1958., 1958), by D. R. Harris, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• SO131 : an IBM-650 code to solve pressure and thermal stress problems in core subassembly plates (Washington, D.C. : Office of Technical Services, Department of Commerce, 1959., 1959), by Carl M. Friedrich, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Dimensional inspection of irradiated PWR Core 1 blanket fuel (Washington, D.C. : Office of Technical Services, Department of Commerce, 1960., 1960), by L. D. Larson, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Evaluation of crud deposits of PWR blanket bundles (Washington, D.C. : Office of Technical Services, Department of Commerce, 1961., 1961), by R. D. Oldenkamp, Y. Solomon, C. F. Paulson, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Measurement of the natural neutron source in two cores (Washington, D.C. : Office of Technical Services, Department of Commerce, 1960., 1960), by W. B. Doub, S. Milani, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Examination of PWR Core 1 blanket fuel rods for microstructure, hydrogen pickup, and burst strength (Washington, D.C. : Office of Technical Services, Department of Commerce, 1961., 1961), by B. Rubin, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Over-all evaluation of blanket fuel removed from PWR Core 1 during the first refueling of the seed (Washington, D.C. : Office of Technical Services, Department of Commerce, 1961., 1961), by F. Schwoerer, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Evaluation of the PWR Core 1 failed element detection and location system (Washington, D.C. : Office of Technical Services, Department of Commerce, 1962., 1962), by C. S. Abrams, F.R. Vaughan, O.D. Parr, P.W. Frank, Bettis Atomic Power Laboratory, Westinghouse Electric Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Examination of PWR Core 1 blanket fuel rods for microstructure changes, hydrogen pickup, burst strength, and fission gas release at the end of the second seed life (Washington, D.C. : Office of Technical Services, Department of Commerce, 1963., 1963), by L. R. Lynam, Bettis Atomic Power Laboratory, Westinghouse Electric Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Metallurgical examination of PWR Core 1 blanket fuel rods at the end of the third seed life (Washington, D.C. : Office of Technical Services, Department of Commerce, 1964., 1964), by L. R. Lynam, Bettis Atomic Power Laboratory, Westinghouse Electric Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Measurement of air blast effects from simulated nuclear reactor core excursions (1957), by Richard J. Larson, Wendell Olson, U.S. Army Ballistic Research Laboratory, and U.S. Atomic Energy Commission (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)
• Yankee critical experiments : b measurements on lattices of stainless steel clad slightly enriched uranium dioxide fuel rods in light water (Pittsburgh, Pennsylvania : Westinghouse Electric Corporation, Atomic Power Dept. ; Washington, D.C. : Available from the Office of Technical Services, Dept. of Commerce, 1959., 1959), by P. W. Davison, J. E. Howard, R. D. Leamer, B. Jennings, D. F. Hanlen, W. H. Bergmann, S. S. Berg, U.S. Atomic Energy Commission, Westinghouse Electric Corporation. Atomic Power Department, and Yankee Atomic Electric Company (page images at HathiTrust)
• Neutron flux peaking and power shapes : a comparison of theory and experiment (Pittsburgh, Pennsylvania : Westinghouse Electric Corporation, Atomic Power Dept. ; Washington, D.C. : Available from the Office of Technical Services, Dept. of Commerce, 1959., 1959), by Robert A. Dannels, Walter J. Eich, U.S. Atomic Energy Commission, Westinghouse Electric Corporation. Atomic Power Department, and Yankee Atomic Electric Company (page images at HathiTrust)
• Reactivity and neutron flux distribution studies in multi-region loaded reactor cores (Pittsburgh, Pennsylvania : Westinghouse Electric Corporation, Atomic Power Department, 1961., 1961), by W. J. Eich, W. P. Kovacik, 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)
• Optimization study for large pressurized water reactor cores (Pittsburgh, Pennsylvania : Westinghouse Electric Corporation, Atomic Power Division, 1964., 1964), by L. E. Strawbridge, R. E. Wolf, U.S. Atomic Energy Commission, and Westinghouse Electric Corporation. Atomic Power Division (page images at HathiTrust)
• Observations of flow characteristics of volume-heated boiling pools (Upton, New York : Brookhaven National Laboratory, Department of Nuclear Energy, Experimental Modeling Group, 1977., 1977), by T. Ginsberg, J. C. Chen, C. E. Schwarz, Owen C. Jones, and Brookhaven National Laboratory. Department of Nuclear Energy. Experimental Modeling Group (page images at HathiTrust)
• Heat transfer and fluid dynamic characteristics of internally heated boiling pools (Upton, New York : Brookhaven National Laboratory, Department of Applied Science, Reactor Safety Experiments Group, 1977., 1977), by W. R. Gustavson, Mujid S. Kazimi, J. C. Chen, and Brookhaven National Laboratory. Department of Applied Science (page images at HathiTrust)
• Naval Research Laboratory report (Naval Research Laboratory :, 1956), by E. H. Bebbs, K. W. Downes, R. H. Vogt, and Naval Research Laboratory (U.S.) (page images at HathiTrust)
• Power removal from a boiling reactor (Oak Ridge, Tennessee : Oak Ridge National Laboratory, 1952., 1952), by Paul Carl Zmola, E. N. Lawson, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Analytical and experimental investigation of a nuclear reactor support structure (Argonne National Laboratory, Reactor Engineering Division, 1965), by A. H. Marchertas, R. O. Brittan, S. H. Fistedis, and Argonne National Laboratory (page images at HathiTrust)
• Thermal hydraulic performance characteristics of EBWR (o to 100 Mwt) (Argonne National Laboratory, Reactor Engineering Division, 1963), by Michael Petrick, E. A. Spleha, and Argonne National Laboratory (page images at HathiTrust)
• Breeding-gain specimens for EBR-I Core IV (Argonne National Laboratory, Metallurgy Division, 1963), by A. B. Shuck and Argonne National Laboratory (page images at HathiTrust)
• Design summary report on the Juggernaut reactor (Argonne National Laboratory, Reactor Engineering Division, 1962), by J. R. Folkrod, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
• Hazard evaluation report on the fast reactor zero power experiment (Zero Power Reactor III) (Argonne National Laboratory, 1961), by R. Rice, H. V. Lichtenberger, B. Cerutti, R. O. Brittan, M. Novick, F. W. Thalgott, R. L. McVean, and J. K. Long (page images at HathiTrust)
• Thermal analysis of type 3 elements in the SM-1, SM-1A and PM-2A cores (U.S. Atomic Energy Commission, Office of Technical Information, 1962), by S. L. Davidson, Alco Products (Firm), and U.S. Atomic Energy Commission (page images at HathiTrust)
• Interim report : FARET experimental program (Argonne National Laboratory, Reactor Engineering Division, 1963), by Argonne National Laboratory (page images at HathiTrust)
• Status report on the Argonne Advanced Research Reactor (Argonne National Laboratory, 1961), by D. H. Lennox and Argonne National Laboratory (page images at HathiTrust)
• Reactor Division (Oak Ridge National Laboratory, 1962), by A. P. Fraas, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Initial testing and operation of the Argonne Low Power Reactor (ALPR) (Argonne National Laboratory, Reactor Engineering Division, 1959), by Eberhard E. Hamer and Argonne National Laboratory (page images at HathiTrust)
• Addendum to the Spert IV hazards summary report : capsule driver core (Idaho Operations Office, U.S. Atomic Energy Commission, 1965), by R. W. Miller, T. F. Lagier, Richard K. McCardell, Phillips Petroleum Company. Atomic Energy Division, U.S. Atomic Energy Commission. Idaho Operations Office, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Zero-power experiments with boiling core B-1, BORAX-V (Argonne National Laboratory, Idaho Division, 1963), by Argonne National Laboratory (page images at HathiTrust)
• Preliminary design of a basic radiation effects reactor (BRER) (Argonne National Laboratory, Reactor Engineering Division, 1961), by D. R. MacFarlane and Argonne National Laboratory (page images at HathiTrust)
• Zero-power experiments on the Argonne Low Power Reactor (ALPR) (Argonne National Laboratory, Reactor Engineering Division, 1961), by D. H. Shaftman and Argonne National Laboratory (page images at HathiTrust)
• Hazards evaluation report associated with the operation of EBWR at 100 MW (Argonne National Laboratory, 1959), by E. A. Wimunc, J. M. Harrer, and Argonne National Laboratory (page images at HathiTrust)
• Radiological aspects of SNAPTRAN 2/10A-3 destructive test (Idaho Operations Office, U.S. Atomic Energy Commission, 1965), by J. R. Fielding, G. A. Dinneen, R. P. Bird, O. L. Cordes, Phillips Petroleum Company. Atomic Energy Division, U.S. Atomic Energy Commission. Idaho Operations Office, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Cleaning and pickling of core components, quality control coupons, subassemblies, and bundles (Pittsburgh, Pennsylvania : Westinghouse Electric Corporation, 1956., 1956), by W. J. Hurford and U.S. Atomic Energy Commission (page images at HathiTrust)
• Safety analysis of the operation of ZPR-3 with fuel loadings up to 430 kg of plutonium : (Addendum to ANL-6504, Safety analysis of plutonium loadings in ZPR-III) (Argonne, Ill. : Argonne National Laboratory, 1965., 1965), by J. K. Long, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
• Developments in the elimination of boron loss from UO2-stainless steel dispersion fuel plates for the argonne advanced research reactor mark I core (Argonne, Illinois. : Argonne National Laboratory, 1968., 1968), by C. Victor Pearson and Argonne National Laboratory (page images at HathiTrust)
• Neutron response analysis in pulsed coupled-core reactors (Los Alamos, New Mexico : Los Alamos Scientific Laboratory of the University of California, 1968., 1968), by George C. Hopkins, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Isothermal hydraulic measurements in fuel elements in Advanced Test Reactor core (Idaho Falls, Idaho : Idaho Nuclear Corporation, National Reactor Testing Station, 1968., 1968), by M. L. Griebenow, U.S. Atomic Energy Commission. Idaho Operations Office, Allied Chemical Corporation, and Aerojet-General Corporation (page images at HathiTrust)
• Mechanical elements operating in sodium and other alkali metals. Volume II, Experience survey (Canoga Park, California. : Liquid Metal Engineering Center, 1970., 1970), by D. J. Kniley, U.S. Atomic Energy Commission, North American Rockwell Corporation. Atomics International Division, and Liquid Metal Engineering Center (U.S.) (page images at HathiTrust)
• LMFBR physics program : GFY 1969 ([Canoga Park, California] : Atomics International, A Division of North American Rockwell Corporation, 1969., 1969), by Rockwell International. Atomics International Division and U.S. Atomic Energy Commission (page images at HathiTrust)

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