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Two-phase flow

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Filed under: Two-phase flow

Choking two-phase flow literature summary and idealized design solutions for hydrogen, nitrogen, oxygen, and refrigerants 12 and 11 (U.S. Govt. Print. Off., 1963), by R. V. Smith and United States. National Bureau of Standards (page images at HathiTrust)
The measurement of two-dimensional phase separation phenomena (The Commission, 1981), by M. Barasch, Richard T. Lahey, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Rensselaer Polytechnic Institute. Department of Nuclear Engineering (page images at HathiTrust)
Countercurrent air/water and steam/water flow above a perforated plate (The Commission :, 1980), by C. Hsieh, Ill.). Department of Chemical Engineering Northwestern University (Evanston, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Entrainment and deposition studies in two-phase cross flow : comparison between air-water and steam-water in a square horizontal duct (The Commission :, 1981), by R. J. Berryman, C. D. Wade, J. C. Ralph, England) Atomic Energy Research Establishment (Harwell, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Pulsed neutron activation measurement of emergency core coolant bypass flow on the LOFT reactor (The Commission :, 1980), by P. Kehler, Argonne National Laboratory, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Technical summary attachment to ECC bypass RIL : topical report (Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Reactor Safety Research ;, 1979), by inc Creare, Christopher J. Crowley, Paul H. Rothe, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Lower plenum voiding : topical report (U.S. Nuclear Regulatory Commission :, 1980), by Paul H. Rothe, Richard G. Sam, inc Creare, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Flow regime identification and void fraction measurement techniques in two-phase flow (The Commission :, 1980), by M. A. Vince, Richard T. Lahey, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Rensselaer Polytechnic Institute. Department of Nuclear Engineering (page images at HathiTrust)
Two phase interactions in countercurrent flow : studies of the flooding mechanism : annual report, November 1975 - October 1977 (The Division :, 1979), by A. E. Dukler, L. Smith, University of Houston. Department of Chemical Engineering, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Preliminary analysis of flashing transients (The Commission :, 1980), by Christopher J. Crowley, Shunling Wei, inc Creare, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Gravity dominated two-phase flow in vertical rod-bundles (The Commission :, 1980), by B. Singh, P. Griffith, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Massachusetts Institute of Technology (page images at HathiTrust)
Theoretical and experimental research on two-phase flow in geothermal well bores : final report (US Dept. of Energy, Division of Geothermal Energy ;, 1981), by James Butz, Gerald Katz, Michael C. Mickley, Denver Research Institute, and United States. Department of Energy. Division of Geothermal Energy (page images at HathiTrust)
First quarter FY80 progress report on the Creare Refill Effects Program. (U.S. Nuclear Regulatory Commission, Division of Reactor Safety Research, Office of Nuclear Regulatory Research. :, 1980), by Christopher J. Crowley, Richard G. Sam, and inc Creare (page images at HathiTrust)
An Investigation of the distribution and entrainment of the ECC water injected into the upper plenum (The Commission, 1980), by D. Bharathan, Thayer School of Engineering, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Problems in modeling of small break LOCA (The Commission, 1980), by N. Zuber and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
A two-dimensional fluid finite element : final report (Division of Project Management, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission ;, 1978), by Massachusetts Institute of Technology. Department of Mechanical Engineering and U.S. Nuclear Regulatory Commission. Division of Project Management (page images at HathiTrust)
Effect of scale on two-phase countercurrent flow flooding (Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, 1979), by H. J. Richter, M. S. Speers, Graham B. Wallis, Thayer School of Engineering, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research (page images at HathiTrust)
Concurrent steam/water flow in a horizontal channel (The Commission, 1981), by U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation and Ill.). Department of Mechanical and Nuclear Engineering Northwestern University (Evanston (page images at HathiTrust)
Two-phase interactions in countercurrent flow studies of the flooding mechanism : progress report, November 1, 1975 - September 30, 1977 (The Division, 1977), by A. E. Dukler, L. Smith, University of Houston. Department of Chemical Engineering, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Model for flow regime transitions for vertical upward gas liquid flow-effect of properties and line size (The Commission, 1977), by A. Taitel, A. E. Dukler, University of Houston. Department of Chemical Engineering, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Contribution to the study of critical flow rates in two-phase water vapor flow (U.S. Nuclear Regulatory Commission, 1977), by M. Reocreux and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
Development of a fluoroscope for studying two-phase flow patterns (Argonne National Laboratory, 1964), by John Johanns, U.S. Atomic Energy Commission, Argonne National Laboratory. Reactor Engineering Division, and Institute of Nuclear Science and Engineering (page images at HathiTrust)
Contribution to the theory of two-phase, one-component critical flow (Argonne National Laboratory, 1962), by Hans K. Fauske, U.S. Atomic Energy Commission, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust)
Local parameters in cocurrent mercury-nitrogen flow (Argonne National Laboratory, 1963), by L. G. Neal, Ill.) Northwestern University (Evanston, Associated Midwest Universities, U.S. Atomic Energy Comission, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust)
The effect of the liquid viscosity in two-phase, two-component flow (Argonne National Laboratory, 1960), by Melvin Jerome Fohrman, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
Calculation procedure for heat transfer to a gas-solid suspension from an externally heated tube (United States Dept. of the Interior, Bureau of Mines, 1970), by M. B. Bransford, John H. Holden, and United States Bureau of Mines (page images at HathiTrust)
Transient analysis of two-phase natural-circulation systems (Argonne National Laboratory, 1962), by J. F. Marchaterre, J. C. Carter, L. T. Bryant, R. P. Anderson, Argonne National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Two-phase pressure drop and burnout using water flowing in round and rectangular channels (Argonne National Laboratory, 1953), by W. H. Jens, P. A. Lottes, Argonne National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Transient analysis of two-phase natural-circulation systems (Argonne National Laboratory, 1962), by J. F. Marchaterre, J. C. Carter, L. T. Bryant, R. P. Anderson, U.S. Atomic Energy Commission, Argonne National Laboratory. Applied Mathematics Division, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust)
Two-phase (liquid-vapor), mass-limiting flow with hydrogen and nitrogen (Washington, 1968), by J. A. Brennan, R. V. Smith, and D. K. Edmonds (page images at HathiTrust)
Longitudinal dispersion in packed extraction columns (Lawrence Radiation Laboratory, 1963), by Alphonse Hennico, Theodore Vermeulen, Jacques Gabriel, and Lawrence Radiation Laboratory (page images at HathiTrust)
Flashing expansion of water through a converging-diverging nozzle (Lawrence Radiation Laboratory, 1961), by Robert Alan Brown and Lawrence Radiation Laboratory (page images at HathiTrust)
Shock location during two-phase flow in an over-expanded nozzle (Lawrence Radiation Laboratory, 1961), by Ross Allan Fiedler and Lawrence Radiation Laboratory (page images at HathiTrust)
Two-phase flow in turbines and reaction nozzles (National Aeronautics and Space Administration; for sale by the Clearinghouse for Federal Scientific and Technical Information, Springfield, Va., 1970), by V. D. Venediktov (page images at HathiTrust; US access only)
Control of the dynamics of a two-phase liquid-gas weightless medium with the aid of surface effects (National Aeronautics and Space Administration, 1967), by V. N. Serebri︠a︡kov (page images at HathiTrust)
Vapor condensing at high velocities ... (National Aeronautics and Space Administration, 1964), by Winthrop E. Hilding, Charles H. Coogan, University of Connecticut, and United States National Aeronautics and Space Administration (page images at HathiTrust)
Flow of boiling liquid (National Aeronautics and Space Administration, 1965), by A. H. Stenning, T. Nejat Veziroglu, University of Miami, and United States National Aeronautics and Space Administration (page images at HathiTrust)
Boiling inception in trichlorotrifluoroethane during forced convection at high pressures (National Aeronautics and Space Administration ;, 1972), by R. S. Dougall, T. E. Lippert, Lewis Research Center, and University of Pittsburgh (page images at HathiTrust)
Subcooled forced convection boiling of trichlorotrifluoroethane (National Aeronautics and Space Administration ;, 1972), by R. S. Dougall, D. J. Panian, Lewis Research Center, and University of Pittsburgh (page images at HathiTrust)
Wind tunnel performance test of coannular plug nozzles (National Aeronautics and Space Adiministration, Scientific and Technical Information Office ;, 1978), by Paul S. Staid and United States. National Aeronautics and Space Administration. Scientific and Technical Information Office (page images at HathiTrust)
Net vapor generation point in boiling flow of trichlorotrifluoroethane at high pressures (National Aeronautics and Space Administration ;, 1973), by R. S. Dougall, T. E. Lippert, Lewis Research Center, and University of Pittsburgh (page images at HathiTrust)
Review of critical flow rate, propagation of pressure pulse, and sonic velocity in two-phase media (National Aeronautics and Space Administration ;, 1972), by Yih-Yun Hsu and Lewis Research Center (page images at HathiTrust)
Experimental pressure drop investigation of wetting and nonwetting mercury condensing in uniformly tapered tubes (National Aeronautics and Space Administration ;, 1966), by James A. Albers, Henry B. Block, and Lewis Research Center (page images at HathiTrust)
Measurement of liquid and two-phase hydrogen densities with a capacitance density meter (National Aeronautics and Space Administration ;, 1969), by George E. Turney, Roger W. Snyder, and Lewis Research Center (page images at HathiTrust)
NASA TN D-6415 (National Aeronautics and Space Administration ;, 1971), by Jerry Smetana, Norman C. Wenger, Lewis Research Center, and United States National Aeronautics and Space Administration (page images at HathiTrust)
Forced-convection peak heat flux on cylindrical heaters in water and refrigerant 113 (National Aeronautics and Space Administration ;, 1974), by Thomas H. Cochran, Charles R. Andracchio, and Lewis Research Center (page images at HathiTrust)
Two-phase hydrogen density measurements by thermal neutron attenuation (National Aeronautics and Space Administration ;, 1965), by Donald F. Shook and Lewis Research Center (page images at HathiTrust)
The integrated pressure drop in two-phase, nonadiabatic flow of hydrogen (Los Alamos Scientific Laboratory of the University of California, 1964), by John R. Bartlit, U.S. Atomic Energy Commission, and Los Alamos Scientific Laboratory (page images at HathiTrust)
Analysis of various types of two-phase annular flow. Part I, Annular flow without liquid entrainment (U.S. Atomic Energy Commission, Division of Technical Information, 1963), by S. Levy, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
Prediction of the pressure loss and density factors for two-phase annular flow with or without heat generation (Knolls Atomic Power Laboratory, General Electric Company, 1957), by J. C. Westmoreland, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
Correlation of liquid fraction in two-phase flow with application to liquid metals (Canoga Park, California : Atomics International, 1963., 1963), by C. J. Baroczy, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
A transient multichannel two-phase hydraulic code (Canoga Park, California : Atomics International, a division of North American Aviation, Inc., 1964., 1964), by L. R. Steele, R. F. Berland, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
Digital code for transient two-phase flow and heat transfer (Atomics International, 1965), by R. C. Noyes, H. H. Cappel, J. G. Morgan, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
A theoretical investigation of the control parameters required to shape the spike phase pulse in two-phase shock tests (Sandia Corporation ;, 1961), by Robert I. Butler and Sandia Corporation (page images at HathiTrust)
A new method for determining the stability of two-phase flow in parallel heated channels with applications to nuclear reactors (Atomics International, 1960), by J. H. Bick, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
Flow patterns of two-phase flow : a survery of literature (New York, New York : Columbia University, Engineering Research Laboratories, 1960., 1960), by John H. Vohr and U.S. Atomic Energy Commission (page images at HathiTrust)
River channel bars and dunes: theory of kinematic waves (U.S. Govt. Print. Off., 1968), by Walter Basil Langbein and Luna B. Leopold (page images at HathiTrust; US access only)
Two-component two-phase flow parameters for low circulation rates (Argonne, Illinois : Argonne National Laboratory, Reactor Engineering Division, 1963., 1963), by Georges E. Smissaert, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
Design basis for critical heat flux condition in boiling water reactors (San Jose, California : General Electric Company, Atomic Power Equipment Department, 1966., 1966), by J. M. Healzer, S. Levy, E. Janssen, J. E. Hench, U.S. Atomic Energy Commission, and General Electric Company. Atomic Power Equipment Department (page images at HathiTrust)
A program of two-phase flow investigation : third quarterly report, October-December, 1963 (San Jose, California : General Electric Company, Atomic Power Equipment Department, 1963., 1963), by F. W. Staub, N. Zuber, U.S. Atomic Energy Commission, and General Electric Company. Atomic Power Equipment Department (page images at HathiTrust)
The low pressure critical discharge of steam-water mixtures from pipes (Richland, Washington : Hanford Atomic Products Operation, 1961., 1961), by F. R. Zaloudek, United States. National Bureau of Standards, United States. Department of Energy. Office of Fusion Energy, Center for Materials Science (National Measurement Laboratory). 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)
Design and construction of an experiment for two-phase flow in fractured porou [i.e. porous] media (Bartlesville Project Office, U.S. Dept. of Energy, 1993), by Rafael E. G. Ayala, Khalid Aziz, Stanford University. Petroleum Research Institute, and United States. Office of the Assistant Secretary for Fossil Energy (page images at HathiTrust)
Self-sustained hydrodynamic oscillations in a natural circulation two-phase-flow boiling loop (Argonne National Laboratory, 1965), by Kamal C. Jain, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
Two-phase heat transfer with gas injection through a porous boundary surface (Argonne National Laboratory, Reactor Engineering Division, 1964), by A. A. Kudirka and Argonne National Laboratory (page images at HathiTrust)
Dynamic analysis of coolant circulation in boiling water nuclear reactors (Argonne National Laboratory, Reactor Physics Division, 1964), by Chathilingath K. Sanathanan and Argonne National Laboratory (page images at HathiTrust)
Pool boiling and initial forced convection tests and analyses (Atomics International, 1964), by H. Lurie, R. C. Noyes, and North American Aviation. Atomics International Division (page images at HathiTrust; US access only)
Prediction of the critical heat flux in forced convection flow (U.S. Atomic Energy Commission, Division of Technical Information, 1962), by S. Levy, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
Two-phase critical flow with application to liquid-metal systems (mercury, cesium, rubidium, potassium, sodium, and lithium) (Argonne National Laboratory, Reactor Engineering Division, 1963), by Hans K. Fauske and Argonne National Laboratory (page images at HathiTrust)
An experimental investigation of two-phase, two-component flow in a horizontal, converging-diverging nozzle (Argonne National Laboratory, Reactor Engineering Division, 1963), by Joseph A. Vogrin and Argonne National Laboratory (page images at HathiTrust)
A photographic study of boiling flow (Oak Ridge, Tennessee : Technical Information Service Extension ; Washington, DC : Office of Technical Services, Department of Commerce, 1963., 1963), by John Henry Vohr, U.S. Atomic Energy Commission. New York Operations Office, and Columbia University. Engineering Research Laboratories (page images at HathiTrust)
Two-phase flow through abrupt expansions and contractions : final report volume III on a study of convection boiling inside channels : June 1966 (Raleigh, North Carolina : North Carolina State University, Department of Chemical Engineering, 1966., 1966), by J. K. Ferrell, John William McGee, and U.S. Atomic Energy Commission. Division of Technical Information (page images at HathiTrust)
Interphase transfer in stationary two-phase media (Oak Ridge, Tennessee : Union Carbide Nuclear Company, Division of Union Carbide Corporation, Oak Ridge Gaseous Diffusion Plant, 1952., 1962), by Stephen Prager, Union Carbide Nuclear Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
Summary of reported droplet size distribution data in dispersed two-phase flow (Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Reactor Safety Research ;, 1978), by R. V. Smith, B. J. Azzopardi, England) Atomic Energy Research Establishment (Harwell, Wichita State University, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Effect of scale on two-phase countercurrent flow flooding in annuli (Washington, D. C. : Nuclear Regulatory Commission [Office of Nuclear Regulatory Research], Division of Reactor Safety Research, 1979-, 1979), by H. J. Richter, Stephen L. Murphy, Thayer School of Engineering, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
An assessment of the literature related to LWR instability modes (Washington, D.C. : Division of Systems Safety, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1980., 1980), by Richard T. Lahey, Donald A. Drew, United States. National Technical Information Service, United States Government Printing Office, Rensselaer Polytechnic Institute. Department of Nuclear Engineering, and U.S. Nuclear Regulatory Commission. Division of Systems Safety (page images at HathiTrust)
Turbulent flow near an oscillating wall (U.S. Beach Erosion Board, 1957), by George Kalkanis (page images at HathiTrust)
Two-phase interactions in countercurrent flow : annual report, November 1977 - December 1978 (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1979., 1979), by A. E. Dukler, R. Semiat, A. Chopra, D. Moalim, University of Houston, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Condensation heat transfer. Part II, Solution of the film condensation problem by successive analytical iteration (Wright-Patterson Air Force Base, Ohio : Directorate of Materials and Processes, Aeronautical Systems Division, Air Force Systems Command, 1963., 1963), by Jon H. Lee and United States. Air Force. Systems Command. Aeronautical Systems Division (page images at HathiTrust)
An integral equation method for boundary interference in a perforated-wall wind tunnel at transonic speeds (Arnold Air Force Base, Tennessee : Arnold Engineering Development Center, Air Force Systems Command, United States Air Force, 1976., 1976), by E. M. Kraft, Arnold Engineering Development Center, United States. Air Force. Systems Command, and Inc ARO (page images at HathiTrust)
Analytical approximation of two-dimensional separated turbulent boundary-layer velocity profiles (Arnold Air Force Base, Tennessee : Arnold Engineering Development Center, Air Force Systems Command, United States Air Force, 1980., 1980), by T. W. Swafford, R. K. Matthews, Inc ARO, Arnold Engineering Development Center, and United States. Air Force. Systems Command (page images at HathiTrust)
Nonlinear control of fluid flow (Arlington, Virginia. : Air Force Office of Scientific Research, 2002., 2002), by Panagiotis D. Christofides, Los Angeles. Department of Chemical Engineering University of California, and United States. Air Force. Office of Scientific Research (page images at HathiTrust)
An investigation of ducted, two-stream, variable-density, turbulent jet mixing with recirculation (Arnold Air Force Base, Tennessee : Arnold Engineering Development Center, Engine Test Facility, Air Force Systems Command, United States Air Force, 1977., 1977), by Roy J. Schulz, United States. Air Force. Systems Command, Arnold Engineering Development Center, and Inc ARO (page images at HathiTrust)
Stability of compressible wake and jet flows (Wright-Patterson Air Force Base, Ohio : Flight Dynamics Laboratory, Air Force Wright Aeronautical Laboratories, Air Force Systems Command, United States Air Force, 1983, 1983), by G. R. Verma, Wilbur L. Hankey, S. J. Scherr, Air Force Wright Aeronautical Laboratories, and Air Force Flight Dynamics Laboratory (U.S.) (page images at HathiTrust)
An investigation of separated flows on two-dimensional models at Mach numbers 5 and 8 (Arnold Air Force Station, Tennessee : Arnold Engineering Development Center, Air Force Systems Command, United States Air Force, 1963., 1963), by A. L. Baer, Inc ARO, Arnold Engineering Development Center, and United States. Air Force. Systems Command (page images at HathiTrust)
Wind tunnel tests of two-dimensional and half-axisymmetric inlet models at Mach numbers 1.5 through 3.0 (Arnold Air Force Base, Tennessee : Arnold Engineering Development Center, Air Force Systems Command, United States Air Force, 1970., 1970), by Frederick K. Hube, Leroy M. Jenke, Inc ARO, Arnold Engineering Development Center, and United States. Air Force. Systems Command (page images at HathiTrust)
Characteristics of axisymmetric and two-dimensional isoenergetic jet mixing zones (Arnold Air Force Station, Tennessee : Arnold Engineering Development Center, Air Force Systems Command, United States Air Force, 1963., 1963), by R. C. Bauer, Inc ARO, Arnold Engineering Development Center, and United States. Air Force. Systems Command (page images at HathiTrust)
Analytical description of the complete two-dimensional turbulent boundary-layer velocity profile (Arnold Air Force Base, Tennessee : Arnold Engineering Development Center, Propulsion Wind Tunnel Facility, Air Force Systems Command, United States Air Force, 1977., 1977), by David L. Whitfield, United States. Air Force. Systems Command, Arnold Engineering Development Center, and Inc ARO (page images at HathiTrust)
Aerodynamic characteristics of perforated walls for transonic wind tunnels (Arnold Air Force Base, Tennessee : Arnold Engineering Development Center, Propulsion Wind Tunnel Facility, Air Force Systems Command, United States Air Force, 1977., 1977), by J. L. Jacocks, United States. Air Force. Systems Command, Arnold Engineering Development Center, and Inc ARO (page images at HathiTrust)
Vortex induced rolling moments on finned missiles at high angle of attack (Boston, Massachusetts : Engineering Laboratories, Boston University, 1968., 1968), by Daniel G. Udelson, United States. |b Air Force. |b Systems Command, Air Force Cambridge Research Laboratories (U.S.), and Boston University (page images at HathiTrust)
Separated flow studies (Wright-Patterson Air Force Base, Ohio : Aerospace Research Laboratories, Air Force Systems Command, 1975., 1975), by Wilbur L. Hankey and Aerospace Research Laboratories (U.S.) (page images at HathiTrust)
Transonic scaling effect on a quasi, two-dimensional C-141 airfoil model (Arnold Air Force Base, Tennessee : Arnold Engineering Development Center, Air Force Systems Command, United States Air Force, 1973., 1973), by C. F. Lo, W. E. Carleton, Arnold Engineering Development Center, United States. Air Force. Systems Command, and Inc ARO (page images at HathiTrust)
Wind tunnel tests of supersonic two-dimensional and half-axisymmetric inlet models in a nonuniform flow field at Mach numbers from 1.5 through 2.5 (Arnold Air Force Base, Tennessee : Arnold Engineering Development Center, Air Force Systems Command, United States Air Force, 1971., 1971), by Frederick K. Hube, Leroy M. Jenke, Inc ARO, Arnold Engineering Development Center, and United States. Air Force. Systems Command (page images at HathiTrust)

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