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Transport theory -- Computer programs

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• Transport theory
• Particles (Nuclear physics) -- Computer programs
• Computer programs

• Neutron transport theory -- Computer programs
• Photon transport theory -- Computer programs
• Radiative transfer -- Computer programs
• Transport theory -- Discrete ordinates method -- Computer programs

• BRYNTRN : a baryon transport model (National Aeronautics and Space Administration, Office of Management, Scientific and Technical Information Division ;, 1989), by John W. Wilson (page images at HathiTrust)
• HZETRN : a heavy ion/nucleon transport code for space radiations (National Aeronautics and Space Administration, Office of Management, Scientific and Technical Information Program, 1991), by John W. Wilson and Langley Research Center (page images at HathiTrust)
• An efficient HZETRN : (a galactic cosmic ray transport code) (National Aeronautics and Space Administration, Office of Management, Scientific and Technical Information Program, 1992), by Judy L. Shinn, John W. Wilson, and Langley Research Center (page images at HathiTrust)
• Improvements in computational accuracy of BRYNTRN (a baryon transport code) (National Aeronautics and Space Administration, Office of Management, Scientific and Technical Information Division ;, 1991), by Judy L. Shinn and Langley Research Center (page images at HathiTrust)
• Effects of fragmentation parameter variations on estimates of galactic cosmic ray exposure : dose sensitivity studies for aluminum shields (National Aeronautics and Space Administration, Office of Management, Scientific and Technical Information Program, 1992), by Lawrence W. Townsend and Langley Research Center (page images at HathiTrust)
• GASP : a computer code for calculating the thermodynamic and transport properties for ten fluids: parahydrogen, helium, neon, methane, nitrogen, carbon monoxide, oxygen, fluorine, argon, and carbon dioxide (National Aeronautics and Space Administration ;, 1975), by Robert C. Hendricks, Anne K. Baron, Ildiko C. Peller, and Lewis Research Center (page images at HathiTrust)
• Theory and use of the general-geometry TWOTRAN program (Los Alamos Scientific Laboratory of the University of California, 1970), by K. D. Lathrop, F. W. Brinkley, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)

• Whirlaway : a three-dimensional, two-group neutron diffusion code for the IBM 7090 computer (U.S. Atomic Energy Commission, 1962), by T. B. Fowler, M. L. Tobias, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• DTF-IV : a FORTRAN-IV program for solving the multigroup transport equation with anisotropic scattering (Los Alamos Scientific Laboratory of the University of California, 1965), by K. D. Lathrop, U.S. Atomic Energy Commission, and Los Alamos Scientific Laboratory (page images at HathiTrust)
• The Sn method and the SNG code (Los Alamos Scientific Laboratory of the University of California, 1959), by Bengt G. Carlson, U.S. Atomic Energy Commission, and Los Alamos Scientific Laboratory (page images at HathiTrust)
• The POT code (Los Alamos Scientific Laboratory of the University of California, 1961), by Clarence E. Lee, U.S. Atomic Energy Commission, and Los Alamos Scientific Laboratory (page images at HathiTrust)
• The TOP code (Los Alamos Scientific Laboratory of the University of California, 1961), by Clarence E. Lee, U.S. Atomic Energy Commission, and Los Alamos Scientific Laboratory (page images at HathiTrust)
• DSN code (Los Alamos Scientific Laboratory of the University of California, 1960), by B. Carlson, Jack Worlton, C. Lee, U.S. Atomic Energy Commission, and Los Alamos Scientific Laboratory (page images at HathiTrust)
• Multigroup P₃ program for the neutron transport equation (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1959), by Richard R. Haefner, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• A monte carlo code for the transport of neutrons (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1959), by William V. Baxter, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Two-space-dimension, multi-group code for the IBM-704 (General Electric, Aircraft Nuclear Propulsion Dept., Atomic Products Division, 1958), by F. M. Trantham, U.S. Atomic Energy Commission, and General Electric Company. Aircraft Nuclear Propulsion Department. Atomic Products Division (page images at HathiTrust)
• Two-space-dimension, multi-group code for the IBM-704 (General Electric, Aircraft Nuclear Propulsion Dept., Atomic Products Division, 1959), by F. M. Trantham, U.S. Atomic Energy Commission, and General Electric Company. Aircraft Nuclear Propulsion Department. Atomic Products Division (page images at HathiTrust)
• An IBM 704 program for the solution of the neutron transport equation in fifty concentric alluli by the Weil method, program I₂ (General Electric, Aircraft Nuclear Propulsion Dept., Atomic Products Division, 1959), by Robert R. McCready, Deborah B. Vollenweider, and General Electric Company. Aircraft Nuclear Propulsion Department. Atomic Products Division (page images at HathiTrust)
• Symbolic matrix translator program Floco-V field-test formulation. (General Electric, Nuclear Materials and Propulsion Operation., 1961), by B. H. Duane, General Electric Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Slowing-down probability in a lattice generated by a three-region cell of finite length (General Electric, Nuclear Materials and Propulsion Operation, 1961), by J. R. Beeler, J. L. McGurn, General Electric Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• directional diffusion coefficients for a lattice generated by a three-region hexagonal cell (General Electric, Nuclear Materials and Propulsion Operation, 1961), by J. R. Beeler, J. D. Popp, General Electric Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Generalized two-space-dimension multigroup coding for the IBM-704 (Knolls Atomic Power Laboratory, General Electric Company, 1957), by Eugene L. Wachspress, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• The FOG one-dimensional neutron diffusion equation codes (Atomics International, 1961), by H. P. Flatt, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• WANDA, a one-dimensional few-group diffusion equation code for the IBM-704 (Washington, D.C. : Office of Technical Services, Department of Commerce, 1959., 1959), by Orville J. Marlowe, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• WANDA, a one-dimensional few-group diffusion equation code for the IBM-704 (Washington, D.C. : Office of Technical Services, Department of Commerce, 1957., 1957), by Orville J. Marlowe, Dorothy S. McCarthy, Culpepper,Linwood M., Carl P. Saalbach, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• PDQ : an IBM-704 code to solve the two-dimensional few-group neutron-diffusion equations (Washington, D.C. : Office of Technical Services, Department of Commerce, 1957., 1957), by Gerald G. Bilodeau, Richard S. Varga, J.G. Fairey, J.P. Dorsey, W.R. Cadwell, Bettis Atomic Power Laboratory, U.S. Atomic Energy Commission, and Westinghouse Electric Corporation (page images at HathiTrust)
• DRACO : a three-dimensional few-group depletion code for the IBM-704 (Washington, D.C. : Office of Technical Services, Department of Commerce, 1958., 1958), by D. S. McCarty, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• TKO : a three-dimensional neutron diffusion equation program for the IBM-704 (Washington, D.C. : Office of Technical Services, Department of Commerce, 1959., 1959), by W. R. Cadwell, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• PDQ-3 : a program for the solution of the neutron-diffusion equations in two dimensions on the IBM-704 (Washington, D.C. : Office of Technical Services, Department of Commerce, 1960., 1960), by W. R. Cadwell, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• SPIC-1 : an IBM-704 code to calculate the neutron distribution outside a right-circular cylindrical source (Washington, D.C. : Office of Technical Services, Department of Commerce, 1959., 1959), by P. Gillis, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• WANDA-5 : a one dimensional neutron diffusion equation program for the Philco-2000 computer (Washington, D.C. : Office of Technical Services, Department of Commerce, 1960., 1960), by Orville J. Marlowe, M. C. Suggs, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• PDQ-4 : a program for the solution of the neutron-diffusion equations in two dimensions on the Philco-2000 computer (Washington, D.C. : Office of Technical Services, Department of Commerce, 1961., 1961), by W. R. Cadwell, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• P3MG1 : a one-dimensional multigroup P-3 program for the Philco-2000 computer (Washington, D.C. : Office of Technical Services, Department of Commerce, 1963., 1963), by Henry Bohl, B.P. Peterson, A.P. Hemphill, B.L. Anderson, E.M. Gelbard, Bettis Atomic Power Laboratory, Westinghouse Electric Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• M0322 and M0332 : FORTRAN programs for calculating neutron absorption in spheres distributed randomly (Washington, D.C. : Office of Technical Services, Department of Commerce, 1962., 1962), by R. M. Cantwell, Bettis Atomic Power Laboratory, Westinghouse Electric Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• PDQ-5: A FORTRAN program for the solution of the two-dimensional neutron-diffusion problem. Part 1. Steady-state version (Washington, D.C. : Office of Technical Services, Department of Commerce, 1963., 1963), by W. R. Caldwell, Bettis Atomic Power Laboratory, U.S. Atomic Energy Commission, and Westinghouse Electric Corporation (page images at HathiTrust)
• Numerical methods and techniques used in the two-dimensional neutron-diffusion program PDQ-5 (Washington, D.C. : Office of Technical Services, Department of Commerce, 1963., 1963), by L. A. Hageman, Bettis Atomic Power Laboratory, Westinghouse Electric Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• SHLOG : a data retrieval program for the Philco-2000 (Washington, D.C. : Office of Technical Services, Department of Commerce, 1963., 1963), by Henry Bohl, B. P. Peterson, Bettis Atomic Power Laboratory, Westinghouse Electric Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• MULE : a FORTRAN program for the calculation of three types of overtone modes (Washington, D.C. : Office of Technical Services, Department of Commerce, 1963., 1963), by R. L. Ewen, Bettis Atomic Power Laboratory, Westinghouse Electric Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• The Peaceman-Rachford method for small mesh increments (Washington, D.C. : Office of Technical Services, Department of Commerce, 1963., 1963), by Willis H. Guilinger, Bettis Atomic Power Laboratory, Westinghouse Electric Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Bettis FORTRAN programming : auxiliary subroutines (Washington, D.C. : Office of Technical Services, Department of Commerce, 1963., 1963), by Orville J. Marlowe, Bettis Atomic Power Laboratory, Westinghouse Electric Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• CTS-3 : a multi-group transport program for infinite cylinders (Washington, D.C. : Office of Technical Services, Department of Commerce, 1963., 1963), by J. H. Bennett, Bettis Atomic Power Laboratory, Westinghouse Electric Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• A digital program to determine the operational characteristics of a pilot-actuated water-relief valve : Bettis Code M0317 (Washington, D.C. : Office of Technical Services, Department of Commerce, 1964., 1964), by D. D. Schultz, Bettis Atomic Power Laboratory, Westinghouse Electric Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• One-space-dimensional multigroup for the IBM 650. Part I, Equations (Knolls Atomic Power Laboratory, General Electric Company, 1955), by G. J. Habetler, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• One-space-dimensional multigroup for the IBM 650. Part II, Machine program (Knolls Atomic Power Laboratory, General Electric Company, 1956), by V. A. Walbran, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• Corn pone : a multigroup, multiregion reactor core (Oak Ridge National Laboratory, 1961), by W. E. Kinney, R. R. Coveyou, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Topic : a fortran program for calculating transport of particles in cylinders (U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by G. E. Putnam, Idaho National Reactor Testing Station, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
• The panda code (Pittsburgh, Pennsylvania : Westinghouse Electric Corporation, Nuclear Energy Systems Division 1975., 1975), by S. Altomare, G. Minton, Westinghouse Electric Corporation. Atomic Power Department, and U.S. Atomic Energy Commission (page images at HathiTrust)

• GAMLEG : a FORTRAN code to produce multigroup cross sections for photon transport calculations (Los Alamos Scientific Laboratory of the University of California, 1965), by K. D. Lathrop, U.S. Atomic Energy Commission, and Los Alamos Scientific Laboratory (page images at HathiTrust)

• Air mass computer program for atmospheric transmittance/radiance calculation : FSCATM (Hanscom AFB, Massachusetts : Air Force Geophysics Laboratory, Air Force Systems Command, United States Air Force, 1983., 1983), by William O. Gallery, S. A. Clough, F. X. Kneizys, and U.S. Air Force Geophysics Laboratory (page images at HathiTrust)

• A user's manual for ANISN : a one dimensional discrete ordinates transport code with anisotropic scattering (Oak Ridge, Tennessee : Oak Ridge Gaseous Diffusion Plant, Union Carbide Corporation Nuclear Division, 1967., 1967), by Ward W. Engle, Union Carbide Corporation. Nuclear Division, Oak Ridge Gaseous Diffusion Plant, and U.S. Atomic Energy Commission (page images at HathiTrust)

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