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Neutron transport theory -- Mathematical models

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• Neutron transport theory
• Nuclear fission -- Mathematical models
• Transport theory -- Mathematical models
• Mathematical models

• Neutron transport theory -- Mathematical models -- Computer simulation
• Neutron transport theory -- Computer simulation

• A spectral theory for the stationary transport operator in slab geometry (Argonne National Laboratory, 1964), by Erwin H. Bareiss, U.S. Atomic Energy Commission, and Argonne National Laboratory. Applied Mathematics Division (page images at HathiTrust)
• The discrete Sn approximation to transport theory (Los Alamos Scientific Laboratory of the University of California, 1962), by Clarence E. Lee, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Neutron flux distributions in multiple region reactors (U.S. Atomic Energy Commission, Technical Information Service, 1951), by S. Wallach, U.S. Atomic Energy Commission, and Westinghouse Electric Corporation. Atomic Power Division (page images at HathiTrust)
• A comparison of some one-velocity transport approximations in lattices (Brookhaven National Laboratory, 1961), by Yuzo Fukai, U.S. Atomic Energy Commission, Brookhaven National Laboratory, and Inc Associated Universities (page images at HathiTrust)
• The energy-dependent Boltzmann equation applied to criticality calculations for bare graphite-moderated reactors (Brookhaven National Laboratory, 1954), by J. A. Fleck, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
• Numerical solution of transient and steady-state neutron transport problems (Los Alamos Scientific Laboratory of the University of California, 1959), by Bengt G. Carlson, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Numerical formulation and solution of neutron transport problems (Los Alamos Scientific Laboratory of the University of California, 1964), by Bengt G. Carlson, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Critical geometries for bare cylinders (Goodyear Atomic Corporation ;, 1956), by J. A. Pond, Goodyear Atomic Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust; US access only)
• RAM-1 : a FORTRAN program to transform and average cross sections from the ROC library tape for use in multigroup neutron transport programs (Washington, D.C. : Office of Technical Services, Department of Commerce, 1965., 1965), by D. R. Harris, A. V. Vota, C. B. Noll, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Mach 1, a one-dimensional diffusion theory package (Argonne National Laboratory, 1966), by D. A. Meneley, D. M. O'Shea, L. C. Kvitek, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)

• HERD 1, 2, and 3 : IBM-704 codes used to solve the one-dimensional, one-velocity transport equation with isotropic scattering (Washington, D.C. : Office of Technical Services, Department of Commerce, 1959., 1959), by Louis A. Hageman, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)

• RANCH : an IBM-704 program used to solve the one-dimensional, single energy neutron transport equation with anisotropic scattering (Washington, D.C. : Office of Technical Services, Department of Commerce, 1961., 1961), by Louis A. Hageman, J. T. Mandel, 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.

• Introduction to the Theory of Neutron Diffusion (volume 1 was only volume published; Los Alamos, NM: Los Alamos Scientific Laboratory, 1953), by Kenneth M. Case, Frederic De Hoffmann, and G. Placzek (page images at HathiTrust)
• The theory of neutron wave propagation : in partial fulfillment of the requirements for the degree of Doctor of Philosophy (1968), by James J. Duderstadt (page images at HathiTrust)
• Buckled spherical harmonics solutions of neutron transport problems (Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Reactor Safety Research, 1979), by R. N. Blomquist, E. E. Lewis, Ill.). Technological Institute Northwestern University (Evanston, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
• Decomposition of the stationary isotropic transport operator in three independent space variables (Argonne National Laboratory, 1964), by Erwin H. Bareiss, U.S. Atomic Energy Commission, and Argonne National Laboratory. Applied Mathematics Division (page images at HathiTrust)
• Two-group diffusion theory for a ring of cylindrical rods (Argonne National Laboratory, 1957), by R. Avery, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
• Multigroup calculations of effective neutron fraction [beta] βeff, prompt neutron lifetime ℓp, and related kinetics parameters for large, fast, plutonium-fueled reactors (Argonne National Laboratory, 1961), by H. A. Sandmeier, U.S. Atomic Energy Comission, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust)
• Calculation of neutron distributions in heterogeneous piles (Technical Information Division, Atomic Energy Commission, 1947), by A. M. Weinberg, U.S. Atomic Energy Commission, and Clinton Laboratories (page images at HathiTrust)
• Thermal neutron flux in the Argonne heavy-water pile (Technical Information Branch, Atomic Energy Commission, 1947), by W. H. Zinn, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
• Diffusion of thermal neutrons (Technical Information Division, Oak Ridge Directed Operations, 1947), by A. M. Weinberg, U.S. Atomic Energy Commission, and Clinton Laboratories (page images at HathiTrust)
• Directional properties of fission neutrons (Atomic Energy Commission, 1946), by Robert R. Wilson, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission Technical Information Division (page images at HathiTrust)
• The twenty grand program for the numerical solution of few-group neutron diffusion equations in two dimensions (Oak Ridge National Laboratory, 1962), by M. L. Tobias, T. B. Fowler, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory. Reactor Division (page images at HathiTrust)
• Zoom : a one-dimensional, multigroup, neutron diffusion theory reactor code for the IBM 704 (University of California Lawrence Radiation Laboratory, 1958), by S. P. Stone, E. E. Dougherty, E. H. Canfield, R. N. Stuart, Lawrence Radiation Laboratory, and Lawrence Livermore Laboratory (page images at HathiTrust)
• Backward Monte Carlo and other methods for "reversing" stochastic processes (Lawrence Radiation Laboratory, 1961), by Edward L. Kaplan and Lawrence Radiation Laboratory (page images at HathiTrust)
• The study of multi-region reactors with an analog computer (U.S. Atomic Energy Commission, 1960), by J. C. Peden, 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. 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, 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. Physics and Instrument Research and Development Operation (page images at HathiTrust)
• Correlation of theoretical and experimental values of the ratio of fast to thermal fissions (U.S. Atomic Energy Commission, 1958), by Lee M. T., 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. Nuclear Physics Research Operation (page images at HathiTrust)
• Neutron diffusion-spherical harmonics theory (Atomic Energy Commission, 1946), by Bengt Carlson, U.S. Atomic Energy Commission, and Los Alamos Scientific Laboratory (page images at HathiTrust)
• Distribution arising from a point source of fast neutrons between two slowing-down media (Atomic Energy Commission, 1946), by R. Bellman, R. E. Marshak, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Some neutron diffusion problems (Atomic Energy Commission, 1946), by R. E. Marshak and U.S. Atomic Energy Commission (page images at HathiTrust)
• Fast-neutron distribution : two infinite plane slowing-down media with point source in one medium (Atomic Energy Commission, 1946), by E. Ostrow and U.S. Atomic Energy Commission (page images at HathiTrust)
• Intensity fluctuations of a neutron chain reactor (Atomic Energy Commission, 1946), by F. de Hoffman and U.S. Atomic Energy Commission (page images at HathiTrust)
• Boundary conditions at interface between medium and vacuum : the extrapolation distance (Atomic Energy Commission, 1947), by A. M. Weinberg, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory (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)
• Studies of the spherical harmonics method in neutron transport theory. Part III., Distribution of the roots of the characteristic equation in the case of anisotropic scattering (Oak Ridge National Laboratory, 1959), by Walter Kofink, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Physics 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)
• A modification of the spherical harmonics method in neutron transport theory (Oak Ridge National Laboratory, 1958), by A. Sauer, U.S. Atomic Energy Commission, Union Carbide Nuclear Company, and Oak Ridge National Laboratory (page images at HathiTrust)
• Boundary values for the inner radius of a cylindrical annular reactor (Oak Ridge National Laboratory, 1958), by E. L. Zimmerman, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Applied Nuclear Physics Division (page images at HathiTrust)
• On Kofink's approximate solution of the neutron transport equation (Oak Ridge National Laboratory, 1958), by Ky Fan, J. J. Andrews, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Mathematics Panel (page images at HathiTrust)
• Relation between PL-and gauss quadrature solutions of the Milne problem (Oak Ridge National Laboratory, 1957), by Walter Kofink, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory. Physics Division (page images at HathiTrust)
• Studies of the spherical harmonics method in neutron transport theory / [Part] II Behavior of the solution of the Milne problem with anisotropic scattering for L -> (infinity symbol) (Oak Ridge National Laboratory, 1957), by Walter Kofink, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory. Physics Division (page images at HathiTrust)
• Neutron slowing down by hydrogen in the consistent P₁ approximation (Oak Ridge National Laboratory, 1956), by Albert Simon, U.S. Atomic Energy Commission, Union Carbide Nuclear Company, and Oak Ridge National Laboratory. Applied Nuclear Physics Division (page images at HathiTrust)
• The effective resonance integral of U²³⁸ metal (Oak Ridge National Laboratory, 1956), by Lawrence Dresner, U.S. Atomic Energy Commission, Union Carbide Nuclear Company, and Oak Ridge National Laboratory. Applied Nuclear Physics Division (page images at HathiTrust)
• Some remarks on the slowing down of neutrons in hydrogen (Oak Ridge National Laboratory, 1956), by L. C. Biedenharn, T. A. Welton, U.S. Atomic Energy Commission, Union Carbide Nuclear Company, and Oak Ridge National Laboratory. Applied Nuclear Physics Division (page images at HathiTrust)
• Calculation of fission-source thermal-neutron distribution in water by the transfusion method (Oak Ridge National Laboratory, 1964), by D. K. Trubey, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Neutron Physics Division (page images at HathiTrust)
• On the accuracy of diffusion theory for neutron moderation (Lawrence Radiation Laboratory, 1964), by J. R. Terrall, 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, United States. Energy Research and Development Administration, U.S. Atomic Energy Commission, and Lawrence Radiation Laboratory (page images at HathiTrust)
• Multigroup one-dimensional spherical harmonic solutions to the Boltzmann transport equation (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by Dale Robert Metcalf, 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)
• NASA TR R-357 (National Aeronautics and Space Administration ;, 1971), by Perry A. Newman, Robert L. Bowden, Virginia Polytechnic Institute and State University, Langley Research Center, and United States National Aeronautics and Space Administration (page images at HathiTrust; US access only)
• A Monte Carlo calculation of the nuclear collision density of primary galactic protons in a slab of aluminum (National Aeronautics and Space Administration :, 1964), by Millard L. Wohl and Lewis Research Center (page images at HathiTrust)
• Transport study of neutron and photon attenuation through lithium hydride and tungsten spherical media (National Aeronautics and Space Administration ;, 1969), by John A. Peoples, Daniel Fieno, United States National Aeronautics and Space Administration, and Lewis Research Center (page images at HathiTrust)
• Neutron diffusion at large distances from the source (U.S. Atomic Energy Commission, Technical Information Branch, 1949), by Hans A. Bethe, Cornell University, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Diffusion and slowing down of neutrons (U.S. Atomic Energy Commission, Technical Information Service, 1952), by Alvin Martin Weinberg, L. C. Noderer, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Neutron diffusion theory : integral theory methods and formulas (U.S. Atomic Energy Commission, Technical Information Division, 1950), by Bengt Carlson, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Estimation of self-absorption in neutron-irradiated samples (U.S. Atomic Energy Commission, Technical Information Service, 1951), by Robert Keyes, Argonne National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Conditions for criticality in certain types of nuclear reactions (U.S. Atomic Energy Commission, Technical Information Service, 1951), by D. S. Selengut, Fairchild Engine and Airplane Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Neutron age calculations in water, graphite, and tissue (U.S. Atomic Energy Commission, Technical Information Branch, 1949), by Alston S. Householder, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Neutron diffusion theory -- the transport approximation (United States Atomic Energy Commission, Technical Information Service, 1950), by Bengt Carlson, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Neutron leakage from hydrogen-moderated systems (Brookhaven National Laboratory, 1955), by Theodore Auerbach, U.S. Atomic Energy Commission, Brookhaven National Laboratory, and Inc Associated Universities (page images at HathiTrust)
• The effect of foil holders on the flux in uranium-water lattices (Brookhaven National Laboratory, 1955), by Theodore Auerbach, U.S. Atomic Energy Commission, Brookhaven National Laboratory, and Inc Associated Universities (page images at HathiTrust)
• Resonance escape probability in slab lattices (Brookhaven National Laboratory, 1958), by Noel Corngold, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Neutron thermilization and diffusion in nonisothermal media (Brookhaven National Laboratory, 1965), by Bal Raj Sehgal, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Solution of the transport equation by Sn approximations (Los Alamos Scientific Laboratory of the University of California, 1955), by Bengt G. Carlson, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Anisotropic scattering approximations in the Boltzmann transport equation (Los Alamos Scientific Laboratory of the University of California, 1964), by Kaye D. Lathrop, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Discrete ordinates angular quadrature of the neutron transport equation (Los Alamos Scientific Laboratory of the University of California, 1965), by Kaye D. Lathrop, Bengt G. Carlson, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Control rod calculation techniques with applications to the Ultra-High Temperature Reactor Experiment (Los Alamos Scientific Laboratory of the University of California, 1965), by B. M. Carmichael, R. J. LaBauve, U.S. Atomic Energy Commission, and Los Alamos Scientific Laboratory (page images at HathiTrust)
• Multigroup Oak Ridge Stochastic Experiment code (M0RSE) (Oak Ridge National Laboratory, 1970), by V.R. Cain, D. C. Irving, P. N. Stevens, E. A. Straker, United States. Defense Atomic Support Agency, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Diffusion and slowing down of neutrons (United States Atomic Energy Commission, Technical Information Service ;, 1956), by Alvin Martin Weinberg, L. C. Noderer, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Neutron cross sections for fast and intermediate nuclear reactors (Los Alamos Scientific Laboratory of the University of California, 1959), by Carroll B. Mills, U.S. Atomic Energy Commission, and Los Alamos Scientific Laboratory (page images at HathiTrust)
• Mechanical quadrature and the transport equation (Los Alamos Scientific Laboratory of the University of California, 1961), by Bengt G. Carlson, Clarence E. Lee, U.S. Atomic Energy Commission, and Los Alamos Scientific Laboratory (page images at HathiTrust)
• Anisotropic scattering in the transport equation : an evaluation of common approximations (Los Alamos Scientific Laboratory of the University of California, 1963), by Kaye D. Lathrop, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Neutron and gamma streaming in void channels (U.S. Atomic Energy Commission, Technical Information Service Extension, 1959), by Peter G. Aline, North American Aviation. Atomics International Division, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (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)
• An analysis of methods in control rod theory and comparisons with experiment (Vallecitos Atomic Laboratory, 1962), by G. H. Kear, M. H. Ruderman, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Space-energy cell homogenization (General Electric, Aircraft Nuclear Propulsion Dept., Atomic Products Division, 1959), by B. H. Duane, M. J. Stanley, and General Electric Company. Aircraft Nuclear Propulsion Department. Atomic Products Division (page images at HathiTrust)
• On the treatment of geometrically thin regions within the two-space dimension multigroup difference equation framework (United States Atomic Energy Commission, Technical Information Service ;, 1955), by E. L. Wachspress, Knolls Atomic Power Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Concerning the multigroup diffusion operator (Knolls Atomic Power Laboratory, General Electric Company, 1957), by M. A. Martino, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• A Monte Carlo calculation of the neutron flux from a monoenergetic point source in air (Sandia Corporation ;, 1959), by C. R. Mehl, U.S. Atomic Energy Commission, and Sandia Corporation (page images at HathiTrust; US access only)
• Transmission of neutrons by cylindrical ducts penetrating radiation shields (Sandia Corporation ;, 1959), by James R. Barcus and Sandia Corporation (page images at HathiTrust; US access only)
• A solution of the neutron transport equation : introduction and part I. (Nuclear Development Associates, 1954), by J. Certaine and U.S. Atomic Energy Commission (page images at HathiTrust)
• Another invertible piecewise greuling solution to the straight ahead transport equation (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service, 1951., 1951), by J. Ernest Wilkins, Alan V. Oppenheim, U.S. Atomic Energy Commission. New York Operations Office, and Inc Nuclear Development Associates (page images at HathiTrust)
• Reconstruction of a function from its moments (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service, 1956., 1956), by J. Certaine, U.S. Atomic Energy Commission. New York Operations Office, and Nuclear Development Corporation of America (page images at HathiTrust)
• Multigroup calculation methods with application to the sodium graphite reactor critical experiment (Atomics International, 1965), by F. L. Fillmore, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Monte Carlo methods and their application to neutron transport problems (Pittsburgh, Pennsylvania. : Bettis Atomic Power Laboratory, 1959., 1959), by Jerome Spanier, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Few group constants for delayed neutrons (Washington, D.C. : Office of Technical Services, Department of Commerce, 1956., 1956), by Lionel Friedman, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• A method of moments for solving the neutron transport equation (Los Alamos, New Mexico : Los Alamos Scientific Laboratory of the University of California, 1965, 1965), by Bengt G. Carlson, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• A solution of the neutron transport equation : Part II, NDA-UNIVAC moment calculations (Nuclear Development Associates, 1955), by J. Certaine, U.S. Atomic Energy Commission. New York Operations Office, and Nuclear Development Corporation of America (page images at HathiTrust)
• On the numerical integration of the neutron transport equation (Oak Ridge, Tennessee : U.S. Atomic Energy Commission, Technical Information Service 1955., 1955), by Herbert Bishop Keller, Jack Heller, U.S. Atomic Energy Commission. New York Operations Office, and New York University. Institute of Mathematical Sciences (page images at HathiTrust)
• Theory of neutron chain reactions. Volume 2, Homogenous nuclear chain reactions (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1951, 1951), by Alvin Martin Weinberg, L. C. Noderer, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Variational boundary conditions for the spherical harmonics approximation to the neutron transport equation (San Jose, California : General Electric Company, Atomic Power Equipment Department, Vallecitos Atomic Laboratory, 1963., 1963), by G. C. Pomraning, Vallecitos Atomic Laboratory, U.S. Atomic Energy Commission, and General Electric Company. Atomic Power Equipment Department (page images at HathiTrust)
• On the energy averaging of the diffusion coefficient (San Jose, California : General Electric Company, Atomic Power Equipment Department, Vallecitos Atomic Laboratory, 1963., 1963), by G. C. Pomraning, Vallecitos Atomic Laboratory, U.S. Atomic Energy Commission, and General Electric Company. Atomic Power Equipment Department (page images at HathiTrust)
• Transport effects in diffusion theory (San Jose, California : General Electric Company, Atomic Power Equipment Department, Vallecitos Atomic Laboratory, 1964., 1964), by G. C. Pomraning, Vallecitos Atomic Laboratory, U.S. Atomic Energy Commission, and General Electric Company. Atomic Power Equipment Department (page images at HathiTrust)
• A method of generating multigroup transfer matrices using an analytic angular integration free of truncation error (Washington, D.C. : Nuclear Regulatory Commission, Office of Inspection and Enforcement, 1978., 1978), by J. A. Bucholz, Oak Ridge National Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Material Safety and Safeguards (page images at HathiTrust)
• RTNS-II utilization plan. (Washington, D. C. : Dept. of Energy, Assistant Secretary of Energy Technology, Office of Fusion Energy, Materials and Radiation Effects Branch, 1978., 1978), by United States. Department of Energy. Materials and Radiation Effects Branch (page images at HathiTrust)
• DTF-II : a one-dimensional, multigroup neutron transport program (Downey, California : North American Aviation, Inc., Atomics International, 1966., 1966), by W. W. Engle, B. W. Colston, M. A. Boling, North Amercian Aviation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Neutron air transport calculations (Livermore, California : Lawrence Radiation Laboratory, U.S. Atomic Energy Commission, 1969., 1969), by Walter M. Webster, Lawrence Radiation Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Finite difference approximations to the neutron diffusion equation (Oak Ridge, Tennessee : USAEC Office of Technical Information Extension, 1960., 1960), by H. P. Flatt, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
• Why a one-dimensional few-group diffusion code for the IBM 1620 (Schenectady, New York : General Electric Company, Knolls Atomic Power Laboratory, 1962., 1962), by R. A. Heffley, C. H. Hunter, Knolls Atomic Power Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Neutron penetration and slowing down at intermediate distances through medium and heavy nuclei (Schenectady, New York : General Electric Company, Knolls Atomic Power Laboratory, 1950., 1950), by Hans A. Bethe, H. Hurwitz, Lewi Tonks, General Electric Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• A Monte Carlo code for gamma-ray transmission through laminated slab shields (Wright Patterson Air Force Base, Ohio : Wright Air Development Center, Air Research and Development Command, United States Air Force, 1958., 1958), by Robert A. Liedtke, Herbert A. Steinberg, United States. Air Force. Air Research and Development Command, and Wright Air Development Center (page images at HathiTrust)
• Equation of state and transport measurements on expanded liquid metals up to 8000K̊ and 0.4 GPa (Dept. of Energy, Lawrence Livermore Laboratory ;, 1978), by William Mark Hodgson, Davis University of California, and Lawrence Livermore Laboratory (page images at HathiTrust)

More items available under broader and related terms at left.