Nuclear reactors -- ReactivitySee also what's at your library, or elsewhere.
Broader terms:Narrower terms:Used for:- Nuclear reactor reactivity
- Reactivity of nuclear reactors
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Filed under: Nuclear reactors -- Reactivity- Conceptual design of a coupled breeding superheating reactor, CBSR / by R. Avery ... [et al.]. (Argonne National Laboratory, 1961), by B. J. Toppel, R. Rohde, W. V. Dewey, R. Avery, Argonne National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
- Decomposition of water in boric acid-cadmium sulfate solutions by reactor radiations (U.S. Atomic Energy Commission, 1955), by William R. McDonell, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
- Shaft seal tests for high-temperature, high-pressure water application (U.S. Atomic Energy Commission, 1954), by A. Smaardyk, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
- Kinetics of Transient Reactor Test as a test reactor (Argonne National Laboratory, 1962), by C. E. Dickerman, J. Gasidlo, R. D. Johnson, U.S. Atomic Energy Commission, and Argonne National Laboratory. Reactor Engineering Division. Idaho Division (page images at HathiTrust)
- Calculation of heterogeneity effects in Zero Power Reactor III fast assemblies using the DSN program (Argonne National Laboratory, 1960), by D. Meneghetti, M. F. Loomis, U.S. Atomic Energy Commission, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust)
- Method for measuring neutron-absorption cross sections by the effect of the reactivity of a chain-reacting pile (Technical Information Division, Oak Ridge Operations, 1947), by W. H. Zinn, G. L. Weil, A. Wattenberg, E. Fermi, H. L. Anderson, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
- Theory of the criticality of the water boiler and the determination of the number of delayed neutrons (Atomic Energy Commission, 1944), by F. de Hoffman and U.S. Atomic Energy Commission (page images at HathiTrust)
- A preliminary nuclear design study of diphenyl moderated and cooled reactors (Argonne National Laboratory, 1955), by E. F. Fricke, Argonne National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
- A cooled-reflector, hot-BeO-core critical experiment (Lawrence Radiation Laboratory, 1961), by G. J. Grammens, H. L. Reynolds, E. Goldberg, R. G. Finke, and Lawrence Radiation Laboratory (page images at HathiTrust)
- k-[infinity] of three weight per cent U²³⁵ enriched UO₃ and UO₂(NO₃)₂ hydrogenous systems (U.S. Atomic Energy Commission, 1961), by V. I. Neeley, R. H. Masterson, J. A. Berberet, 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. Hanford Laboratories Operation (page images at HathiTrust)
- Xenon instability in graphite reactors (U.S. Atomic Energy Commission, 1961), by G. C. Fullmer, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust)
- Meleager : a burn-up code for fuel cycle analysis (U.S. Atomic Energy Commission, 1961), by J. R. Triplett, G. J. Busselman, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, United States. National Bureau of Standards. Fracture and Deformation Division, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust)
- A calculation of the reactivity worth of plutonium and uranium-235 as enrichment in thermal reactors (U.S. Atomic Energy Commission, 1959), by D. P. Granquist, 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. Programming Operation (page images at HathiTrust)
- A critical assembly for the measurement of lattice reactivity (Hanford Works, 1952), by J. Ozeroff, Hanford Works, and U.S. Atomic Energy Commission (page images at HathiTrust)
- The fast multiplication effect of beryllium oxide in reactors (Oak Ridge National Laboratory, 1960), by W. H©·afele, Marina Tsagaris, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Analytical Chemistry Division (page images at HathiTrust)
- Chemical feasibility of homogenous neutron poisons for criticality contols in Consolidated Edison fuel processing solutions (Oak Ridge National Laboratory, 1960), by J. G. Moore, R. H. Rainey, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Chemical Technology Division. Chemical Development Section B. (page images at HathiTrust)
- Effective cadmium cutoff energies : supplement (Oak Ridge National Laboratory, 1960), by R. W. Stoughton, M. P. Lietzke, J. Halperin, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Chemistry Division (page images at HathiTrust)
- An IBM-704 code for a harmonics method applied to two-region spherical reactors (Oak Ridge National Laboratory, 1960), by R. Chalkley, M. L. Tobias, C. W. Nestor, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Reactor Experimental Engineering Division (page images at HathiTrust)
- Power excursions in the HRT (Oak Ridge National Laboratory, 1960), by M. W. Rosenthal, M. Tobias, S. Jaye, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Reactor Experimental Engineering Division (page images at HathiTrust)
- The fast-neutron multiplication effect of beryllium in reactors (Oak Ridge National Laboratory, 1959), by W. H©·afele, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Neutron Physics Division (page images at HathiTrust)
- Operational safety of the ORNL graphite reactor using enriched-uranium fuel (Oak Ridge National Laboratory, 1960), by P. R. Kasten, M. P. Lietzke, S. Jaye, U.S. Atomic Energy Commission, Union Carbide Corporation, 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)
- Experiments on the kinetics of the HRE (Oak Ridge National Laboratory, 1957), by V. K. Paré, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory Reactor Experimental Engineering Division (page images at HathiTrust)
- Operational safety of the homogenous reactor test (Oak Ridge National Laboratory, 1956), by P. R. Kasten, U.S. Atomic Energy Commission, Union Carbide Nuclear Company, and Oak Ridge National Laboratory. Reactor Experimental Engineering Division (page images at HathiTrust)
- The buildup of heavy isotopes during thermal neutron irradiation of uranium reactor fuels (Oak Ridge National Laboratory, 1957), by J. O. Blomeke, U.S. Atomic Energy Commission, Union Carbide Nuclear Company, and Oak Ridge National Laboratory. Chemical Technology Division (page images at HathiTrust)
- Army package power reactor critical experiment (Oak Ridge National Laboratory, 1957), by J. K. Leslie, W. R. Johnson, M. L. Batch, D. W. Magnuson, D. V. P. Williams, U.S. Atomic Energy Commission, Union Carbide Nuclear Company, and Oak Ridge National Laboratory. Applied Nuclear Physics Division (page images at HathiTrust)
- Design and thermal analysis of EGCR control rods (Oak Ridge National Laboratory, 1964), by J. W. Michel, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Reactor Division (page images at HathiTrust)
- Analysis of fast transient reactivity effects in the Spert I water-moderated, UO₂-fueled core (Idaho Operations Office, U.S. Atomic Energy Commission, 1965), by A. H. Spano, J. E. Houghtaling, Phillips Petroleum Company. Atomic Energy Division, U.S. Atomic Energy Commission. Idaho Operations Office, and Idaho National Reactor Testing Station (page images at HathiTrust)
- Tables of reactivity vs. period for U²³⁵, Pu²³⁹, and U²³³ (U.S. Atomic Energy Commission, Idaho Operations Office, 1958), by K. V. Moore and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
- Theory of power transients in the SPERT I reactor : final report (U.S. Atomic Energy Commission, Idaho Operations Office, 1958), by W. A. Horning, H. C. Corben, Phillips Petroleum Company. Atomic Energy Division, and Ramo-Wooldridge Corporation (page images at HathiTrust)
- Plutonium system study with an application to the materials testing reactor (U.S. Atomic Energy Commission, Idaho Operations Office, 1958), by W. Bennett Lewis, G. D. Marshall, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
- Reactivity measurements in the engineering test reactor critical facility (U.S. Atomic Energy Commission, Idaho Operations Office, 1958), by Earl E. Burdick, J. W. Henscheid, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
- Stability analysis of the engineering test reactor with reactivity feedback through the temperature coefficient (U.S. Atomic Energy Commission, Idaho Operations Office, 1958), by S. R. Gossmann and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
- A statistical determination of the reduced prompt neutron generation time, [lambda]/[beta], in the SPERT IV reactor (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by Roger Lee Johnson, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
- Predicting excess reactivity in the ETR as a function of power-time (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by J. W. Henscheid, E. E. Burdick, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
- The effects of pressure and flow on room temperature power excursions in SPERT III (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by C. R. Toole, 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)
- 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)
- A transport study of the neutron flux, adjoint, and importance for the advanced reactivity measurement facility-II (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by N. C. Kaufman, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (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)
- Shutdown reactivity by the modified rod drop method (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by K. V. Moore, 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)
- Xenon-135 induced instabilities of the neutron flux in nuclear reactors (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by Gary Marlin Sandquist, 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)
- An analysis of the accuracy of perturbation theory (U.S. Atomic Energy Commission, Technical Information Service, 1954), by J. W. Webster 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)
- 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)
- Weighing functions for calculating reactivity perturbations in the MTR (U.S. Atomic Energy Commission, Technical Information Service, 1953), by J. W. Webster and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
- The low cross-section fission product poisons (U.S. Atomic Energy Commission, Technical Information Service, 1953), by J. W. Webster 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)
- Methods for calculating large reactivity changes in the MTR (U.S. Atomic Energy Commission, Technical Information Service, 1954), by H. L. McMurry and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
- Reactor calculations on the card-programmed calculator (U.S. Atomic Energy Commission, Technical Information Service Extension, 1955), by D. D. Dix and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
- A critical assembly having maximum sensitivity (U.S. Atomic Energy Commission, Technical Information Service, 1953), by J. W. Webster and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
- Reactivity measurements facility manual for initial startup (U.S. Atomic Energy Commission, Technical Information Service, 1954), by S. G. Forbes and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
- Calculations of reactivity behavior during SPERT-I transients (U.S. Atomic Energy Commission, Idaho Operations Office, 1957), by R. W. Miller and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
- Note on the effect on reactivity of water annuli in large void spaces in the Spert-I reactor core (U.S. Atomic Energy Commission, Idaho Operations Office, 1957), by G. O. Bright, C. R. Toole, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
- Kinetic studies on the Spert I reactor. [Part] I, Initial behavior by the energy model (U.S. Atomic Energy Commission, Idaho Operations Office, 1958), by George W. Griffing, L. I. Deverall, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
- Theory of power transients in the SPERT I reactor (U.S. Atomic Energy Commission, Idaho Operations Office, 1958), by R. S. Margulies, Garrett Birkhoff, W. A. Horning, H. C. Corben, Phillips Petroleum Company. Atomic Energy Division, and Ramo-Wooldridge Corporation (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, U.S. Atomic Energy Commission, 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)
- 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, U.S. Atomic Energy Commission, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
- Temperature coefficients of the reactivity measurement facility (U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by E. Fast, U.S. Atomic Energy Commission, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
- An analysis of nonboiling reactivity feedback mechanisms in pressurized power excursions in the SPERT III reactor (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by Richard W. Garner, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
- An integral method for identifying neutron flux spectra (U.S. Atomic Energy Commission, Idaho Operations Office, 1960), by Robert G. Nisle, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
- The dependence of reactor behavior on the self-shutdown mode (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by S. G. Forbes, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
- Review of several models for power behavior and reactivity feedback in reactor excursion studies (U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by Richard W. Garner, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
- Reactor physics studies for the final conceptual design of the advanced test reactor (U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by A. W. Brown, R. S. Marsden, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (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)
- Analysis of self-shutdown behavior in the SPERT I reactor (U.S. Atomic Energy Commission, Idaho Operations Office, 1959), by S. G. Forbes, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
- Analysis and experiments with a pulsed neutron source for an unreflected solution reactor up to $50 shutdown (National Aeronautics and Space Administration ;, 1969), by Daniel Fieno, C. Ford, Robert A. Mueller, Thomas A. Fox, Lewis Research Center, and United States National Aeronautics and Space Administration (page images at HathiTrust)
- Criticality experiments and analysis of molybdenum-reflected cylindrical uranyl-fluoride-water solution reactors (National Aeronautics and Space Administration ;, 1972), by Daniel Fieno, Robert Mueller, Thomas Fox, and Lewis Research Center (page images at HathiTrust)
- Perturbation theory and applications (U.S. Atomic Energy Commission, Technical Information Service, 1954), by H. L. McMurry, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
- Experimental investigation of the self-limitation of power during reactivity transients in a subcooled, water-moderated reactor : Borax-I experiments, 1954 (U.S. Atomic Energy Commission, Technical Information Service, 1955), by J. R. Dietrich, Argonne National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
- Criticality of the water boiler and effective number of delayed neutrons (U.S. Atomic Energy Commission, Technical Information Service, 1951), by F. de Hoffmann, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
- Temperature coefficient of reactivity in the converter reactor (U.S. Atomic Energy Commission, Technical Information Service, 1956), by L. B. Robinson, North American Aviation, and U.S. Atomic Energy Commission (page images at HathiTrust)
- The effect of gaps on pile reactivity (U.S. Atomic Energy Commission, Technical Information Service ;, 1955), by Stephen Tamor, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
- On the derivation and integration of the pile-kinetic equations (U.S. Atomic Energy Commission, Technical Information Branch, 1949), by H. Hurwitz, U.S. Atomic Energy Commission, and Knolls Atomic Power Laboratory (page images at HathiTrust)
- Temperature coefficient of the liquid metal fuel reactor (United States Atomic Energy Commission, Technical Information Service, 1955), by J. Fleck, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
- Temperature coefficients of reactivity of reactors (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)
- Reactivity coefficient measurement of buckling (United States Atomic Energy Commission, Technical Information Service, 1955), by Kenneth W. Downes, Herbert J. Kouts, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
- Uniform temperature coefficient of the BNL reactor (United States Atomic Energy Commission, Technical Information Service Extension, 1955), by J. Chernick, J. W. Kunstadter, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
- Subcritical barometric coefficient of the BNL reactor (United States Atomic Energy Commission, Technical Information Service Extension, 1955), by J. Chernick, A. Ḳaplan, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
- Hot rod experiment (United States Atomic Energy Commission, Technical Information Service Extension, 1955), by J. Chernick, J. W. Kunstadter, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
- Simulated barometric coefficient (United States Atomic Energy Commission, Technical Information Service Extension, 1955), by J. Chernick, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
- Temperature of and stresses in cylindrical fuel elements during pile flashes : application to Brookhaven reactor / Melville Clark, Jr. (Brookhaven National Laboratory, 1950), by Melville Clark, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
- The effect of variable local multiplication on the statics of a reactor (Brookhaven National Laboratory, 1951), by J. Chernick, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
- A review of nonlinear reactor dynamics problems (Brookhaven National Laboratory, 1962), by Jack Chernick, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (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)
- Reactor power transients as calculated by the space independent reactor equations (U.S. Atomic Energy Commission, Idaho Operations Office, 1959), by K. V. Moore, W. J. Byron, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
- Perturbation theory and applications. [Part] I, Theoretical (U.S. Atomic Energy Commission, Idaho Operations Office, 1956), by H. L. McMurry, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
- Reactivity measurements with the bulk shielding reactor (U.S. Atomic Energy Commission, Technical Information Service, 1954), by E. B. Johnson, T.E. Cole, J. L. Meem, R. G. Cochran, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory (page images at HathiTrust)
- Applied Nuclear Physics Division. (Oak Ridge National Laboratory, 1956), by F. G. Prohammer, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory (page images at HathiTrust)
- Critical studies of the Southwest Experimental Fast Oxide Reactor (SEFOR) in ZPR-3 : (assembly 47) (Argonne National Laboratory, Idaho Division, 1967), by J. K. Long, A. M. Leridon, J. A. Kremser, A. Weitzberg, R. L. McVean, U.S. Atomic Energy Commission, and Argonne National Laboratory. Idaho Division (page images at HathiTrust)
- The subroutine used to calculate design basis accidents for the ZPR-6 and -9 plutonium safety analysis report (ANL-7442) (Argonne National Laboratory, Reactor Physics Division, 1968), by G. K. Rusch, J. M. Van Doorninck, U.S. Atomic Energy Commission, and Argonne National Laboratory. Reactor Physics Division (page images at HathiTrust)
- A variational method for calculating geometrical bucklings (Hanford Atomic Products Operation, 1958), by G. D. Joanou, General Electric Company, Hanford Atomic Products Operation, and U.S. Atomic Energy Commission (page images at HathiTrust)
- Preliminary critical experiments on a mock-up of the Los Alamos Molten Plutonium Reactor (Los Alamos Scientific Laboratory of the University of California, 1958), by R. E. Peterson, R. M. Kiehn, D. M. Holm, H. G. Barkmann, U.S. Atomic Energy Commission, and Los Alamos Scientific Laboratory (page images at HathiTrust)
- The period equilibrium effect in reactor dynamics (Los Alamos Scientific Laboratory of the University of California, 1962), by Sidney Singer, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
- Ultra high temperature reactor critical experiment (UCX) safety analysis report (Los Alamos Scientific Laboratory of the University of California, 1965), by U.S. Atomic Energy Commission and Los Alamos Scientific Laboratory. K-Division (page images at HathiTrust)
- Critical calculations for half-filled ISHR sphere (United States Atomic Energy Commission, Technical Information Extension, 1955), by M. Tobias, Paul N. Haubenreich, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory (page images at HathiTrust)
- Kinetic experiments (U.S. Atomic Energy Commission, Technical Information Service ;, 1955), by V. K. Par©Øe, Sidney Visner, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory (page images at HathiTrust)
- Reactivity effects of non-uniform density changes in HRT (United States Atomic Energy Commission, Technical Information Service ;, 1955), by V. K. Par©Øe, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
- Temperature coefficients and maximum rates of increase of reactivity for HRT (United States Atomic Energy Commission, Technical Information Extension ;, 1955), by V. K. Par©Øe, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
- Thorium breeder reactors following rapid addition of reactivity (Oak Ridge National Laboratory, 1956), by M. W. Rosenthal and U.S. Atomic Energy Commission (page images at HathiTrust)
- Core-temperature excursions following a piping failure in the Plutonium Recycle Test Reactor (Battelle Memorial Institute ;, 1959), by Robert B. Filbert, Lewis E. Hulbert, Carl A. Alexander, Alexis W. Lemmon, 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)
- Experimental investigations of reactor transients (Idaho Operations Office, U.S. Atomic Energy Commission, 1956), by T. R. Wilson, F. Schroeder, G. O. Bright, F. L. Bentzen, S. G. Forbes, Warren E. Nyer, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
- An evaluation of effective plutonium cross sections in reactivity calculations : study of slightly-enriched uranium-water lattices with high conversion ratio (Combustion Engineering, Inc., 1961), by E. Fein, L. C. Noderer, U.S. Atomic Energy Commission, and inc Combustion Engineering (page images at HathiTrust; US access only)
- Calculation of reactor transients (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1960), by H. Dean Brown, Duncan Randall, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
- Reactivity measurements in a subcritical pile (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1955), by Robert C. Axtmann, T. F. Parkinson, G. Dessauer, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
- Reactivity comparisons between cobalt and lithium-aluminum alloy (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1957), by Harold R. Fike, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
- Reactivity versus number of neutrons captured in control materials (United States Atomic Energy Commission, Office of Technical Information ;, 1960), by Walter L. Morgan, John L. Russell, U.S. Atomic Energy Commission, and General Electric Company (page images at HathiTrust)
- Absorber burn-up experiment interim report : technical report (United States Atomic Energy Commission, Office of Technical Information ;, 1961), by John L. Russell, Walter V. Mosgovoy, Morton R. Carrothers, U.S. Atomic Energy Commission, and General Electric Company (page images at HathiTrust)
- Calculation of Doppler coefficient and other safety parameters for a large fast oxide reactor (United States Atomic Energy Commission, Office of Technical Information ;, 1961), by P. Greebler, J. R. Sueoka, B. A. Hutchins, U.S. Atomic Energy Commission, and General Electric Company. Atomic Power Equipment Department (page images at HathiTrust)
- AEC Superheat criticals : a comparison of experiment and theory on uniform lattices (General Electric Company, Atomic Power Equipment Dept., 1962), by G. T. Peteresen, F. G. Warzek, U.S. Atomic Energy Commission. Division of Technical Information, and General Electric Company. Atomic Power Equipment Department (page images at HathiTrust)
- Absorber burn-up experiment final report (U.S. Atomic Energy Commission, Division of Technical Information, 1962), by John L. Russell, Walter V. Mosgovoy, Morton R. Carrothers, U.S. Atomic Energy Commission, and Vallecitos Atomic Laboratory (page images at HathiTrust)
- Doppler calculations for large fast ceramic reactors (U.S. Atomic Energy Commission, Division of Technical Information, 1962), by P. Greebler, A. Goldman, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
- Critical mass calculations for bare hydrogen moderated reactors by means of transport theory (Technical Information Service, 1952), by David Selengut, Aircraft Nuclear Propulsion Project (General Electric Company), and U.S. Atomic Energy Commission (page images at HathiTrust)
- Two-space-dimension multigroup analysis of a moving-fuel reactor (Knolls Atomic Power Laboratory, General Electric Company, 1955), by Eugene L. Wachspress, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust; US access only)
- Neutron moderation by chemically bound hydrogen (Atomics International, 1959), by E. U. Vaughan, E. R. Cohen, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
- Analysis of SNAP Transient-3 destructive experiment (Canoga Park, California : Atomics International, 1965., 1965), by J.O. Zane, A. Weitzberg, Paddleford,D.F., L.I. Moss, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
- SRE reactivity history program (Canoga Park, California : Atomics International, 1964., 1964), by L. M. Weaver, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
- An electrical resistivity study of lattice defects introduced in copper by 1.25 Mev electron irradiation at 80°K (Atomics International, 1956), by C. J. Meechan, J. A. Brinkman, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
- Stability studies on fast reactors with delayed reactivity coefficients (Washington, D.C. : Department of Commerce, Office of Technical Services, 1961., 1961), by J. Agresta, H. Soodak, United Nuclear Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
- A hazards summary for routine operation of the bulk shielding reactor at one megawatt (Oak Ridge, Tennessee : Oak Ridge National Laboratory, [1955], 1954), by F. C. Maienschein, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
- Extended comparison of calculated and measured reactivities for D₂O-moderated lattices (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1962., 1962), by R. Sullivan, J. H. Hutton, Harry Soodak, United Nuclear Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
- Critical experiments on a highly enriched homogeneous reactor (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 J. R. Brown, W. O. Bateson, B. H. Noordhoff, Westinghouse Electric Corporation. Atomic Power Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
- Reactor criticality and non-negative matrices (Pittsburgh, Pennsylvania. : Bettis Plant, 1957., 1957), by Garrett Birkhoff, Richard S. Varga, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
- Experimental and theoretical study of critical slabs : effect of different reflector arrangements and compositions (Pittsburgh, Pennsylvania. : Bettis Plant, 1957., 1957), by C. E. McFarland, L. O. Herwig, A. D. Voorhis, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
- Temperature coefficients of a highly enriched core in slab geometry (Washington, D.C. : Office of Technical Services, Department of Commerce, 1959., 1959), by S. L. Shufler, H.I. Dolnick, R.S. Wick, W.F. Vogelsang, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
- An experiment to measure effective delayed neutron fractions (Washington, D.C. : Office of Technical Services, Department of Commerce, 1960., 1960), by S. Kaplan, A. F. Henry, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
- Nuclear analysis of thermal reflected cylindrical homogeneous critical assemblies (Washington, D.C. : Office of Technical Services, Department of Commerce, 1960., 1960), by Gene P. Rutledge, P. A. Kantorczyk, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
- The startup experiment program for the Yankee reactor (Pittsburgh, Pennsylvania : Westinghouse Electric Corporation, Atomic Power Dept. ; Washington, D.C. : Available from the Office of Technical Services, Dept. of Commerce, 1961., 1961), by J. M. Gallagher, U.S. Atomic Energy Commission, Westinghouse Electric Corporation. Atomic Power Department, and Yankee Atomic Electric Company (page images at HathiTrust)
- Analysis of the reactivity characteristics of Yankee Core I (Pittsburgh, Pennsylvania : Westinghouse Electric Corporation, Atomic Power Division, 1963., 1963), by C. G. Poncelet, Westinghouse Electric Corporation. Atomic Power Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
- CNCR-2 : a one-dimensional few group depletion code for the IBM-7090, which includes the effects of water density variations on neutron moderation (Pittsburgh, Pennsylvania : Westinghouse Electric Corporation, Atomic Power Division, 1964., 1964), by S. M. Hendley, R. A. Mangan, Westinghouse Electric Corporation. Atomic Power Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
- TURBO : a two dimensional few-group depletion code for the IBM-7090 (Pittsburgh, Pennsylvania : Westinghouse Electric Corporation, Atomic Power Division, 1964., 1964), by S. M. Hendley, R. A. Mangan, Westinghouse Electric Corporation. Atomic Power Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
- Unit cell homogenization for reactor depletion studies (Pittsburgh, Pennsylvania : Westinghouse Electric Corporation, Atomic Power Division, 1964., 1964), by Harald A. Risti, Westinghouse Electric Corporation. Atomic Power Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
- Instability studies with EBR-I, Mark III (Argonne, Illinois : Argonne National Laboratory, Idaho Division, 1960., 1960), by R. R. Smith, U.S. Atomic Energy Commission, and Argonne National Laboratory (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)
- A measurement of eta and other fission parameters for U-233, PU-239, and PU-241, relative to U-235, at sub-cadmium neutron energies (Knolls Atomic Power Laboratory, General Electric Company, 1955), by D. E. McMillan, T. M. Snyder, E. R. Gaerttner, J. B. Sampson, M. E. Jones, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
- The self-regulation by moderator boiling in stainless steel-UO₂-H₂O reactors (White Plains, New York : Nuclear Development Corporation of America, 1955., 1955), by Louise Gartner, Robert Daane, U.S. Atomic Energy Commission, and Nuclear Development Corporation of America (page images at HathiTrust)
- Effective cadmium cutoff energies (Oak Ridge, Tennessee : U.S. Atomic Energy Commission, Technical Information Service, 1960., 1960), by R. W. Stoughton, Marjorie P. Lietzke, J. Halperin, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Chemistry Division (page images at HathiTrust)
- Idaho Division summary report : October 1961 through September 1962 (Argonne National Laboratory, Idaho Division, 1962), by Meyer Novick and Argonne National Laboratory (page images at HathiTrust)
- Idaho Division summary report : October 1960 through March 1961 (Argonne National Laboratory, Idaho Division, 1961), by Meyer Novick and Argonne National Laboratory (page images at HathiTrust)
- The period effect in reactor dynamics (Argonne National Laboratory, Reactor Engineering Division, 1964), by Joseph C. Carter, Jack H. Tessier, David W. Sparks, and Argonne National Laboratory (page images at HathiTrust)
- Idaho Division summary report : July, August, September, 1960 (Argonne National Laboratory, Idaho Division, 1960), by Meyer Novick and 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)
- EBR-II dry critical experiments : Experimental program, experimental procedures, and safety considerations (Argonne National Laboratory, Reactor Engineering Division, 1961), by L. J. Koch and Argonne National Laboratory (page images at HathiTrust)
- Hazards summary report for the Hanford plutonium critical mass laboratory (Hanford Atomic Products Operation, 1960), by W. A. Reardon, U.S. Atomic Energy Commission, Hanford Atomic Products Operation, and General Electric Company (page images at HathiTrust)
- Weighting functions for calculating reactivity perturbations in the MTR (U.S. Atomic Energy Commission, Technical Information Service, 1955), by J. W. Webster, U.S. Atomic Energy Commission, and Phillips Petroleum Company. Atomic Energy Division (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)
- Simulation of reactor dynamics : Volume 1, A description of AIROS-II-A / by R. A. Blaine, R. F. Berland. (Downey, California : North American Aviation, Inc., Atomics International, 1967., 1967), by R. A. Blaine, R. F. Berland, North Amercian Aviation, and U.S. Atomic Energy Commission (page images at HathiTrust)
- High temperature measurements of doppler effect in UC and UO₂ by method of temperature-cycled reactivity oscillation (Downey, California : North American Aviation, Inc., Atomics International, 1967., 1967), by L. S. Beller, W. H. Heneveld, North Amercian Aviation, and U.S. Atomic Energy Commission (page images at HathiTrust)
- Elementary neutronics considerations in LMFBR design (Argonne, Illinois. : Argonne National Laboratory, 1969., 1969), by G. H. Golden and Argonne National Laboratory (page images at HathiTrust)
- Phyusics methods used to compute reactivity, [lambda]/©�eff, and rod worth for the PBF critical experiments (Washington, D. C. : National Reactor Testing Station, U.S. Atomic Energy Commission, 1968., 1968), by B. L. Rushton, Phillips Petroleum Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
- CMB-5 health and safety manual (Los Alamos, New Mexico : Los Alamos Scientific Laboratory of the University of California, 1972., 1972), by W. N. Miner, F. W. Schonfeld, D. L. Douglass, R. O. Elliott, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
- The reactivity of the JEEP as a function of control plate position (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service, 1951., 1951), by M. Bogaardt, Joint Establishment for Nuclear Energy Research (Netherlands and Norway), and U.S. Atomic Energy Commission (page images at HathiTrust)
- Some remarks on the influence of the expansion of heavy water on the reactivity of a nuclear reactor (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service, 1952., 1952), by M. Bogaardt, Joint Establishment for Nuclear Energy Research (Netherlands and Norway), and U.S. Atomic Energy Commission (page images at HathiTrust)
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