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Nuclear reactors -- Cooling -- Congresses

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Filed under: Nuclear reactors -- Cooling -- Congresses

Proceedings of the U.S. Nuclear Regulatory Commission ... Water Reactor Safety Research Information Meeting. (Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, in the 20th century), by Water Reactor Safety Research Information Meeting, United States. National Bureau of Standards, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research (page images at HathiTrust)
Meeting on Recator Vessel Liquid Level Measurement. (Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission :, 1981), by Md.) U.S. Nuclear Regulatory Commission. Meeting on Reactor Vessel Liquid Level Measurement (1980 : Gaithersburg, N. N. Kondic, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)

Filed under: Fast reactors -- Cooling -- Congresses

Proceedings of the International Meeting on Fast Reactor Safety and Related Physics, October 5-8, 1976, Chicago, Illinois (ERDA ;, 1977), by Ill.) International Meeting on Fast Reactor Safety and Related Physics (1976 : Chicago, United States. Energy Research and Development Administration, European Nuclear Society, and American Nuclear Society (page images at HathiTrust)

Filed under: Pressurized water reactors -- Cooling -- Congresses

Meeting on Recator Vessel Liquid Level Measurement. (Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission :, 1981), by Md.) U.S. Nuclear Regulatory Commission. Meeting on Reactor Vessel Liquid Level Measurement (1980 : Gaithersburg, N. N. Kondic, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)

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Filed under: Nuclear reactors -- Cooling

Emergency core cooling; report. (U.S. Atomic Energy Commission, 1967), by United States. Advisory Task Force on Power Reactor Emergency Cooling and U.S. Atomic Energy Commission (page images at HathiTrust; US access only)
Safety evaluation report on Westinghouse Electric Company ECCS evaluation model for plants equipped with upper head injection (Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Systems Safety ;, 1978), by G. N. Lauben and U.S. Nuclear Regulatory Commission. Division of Systems Safety (page images at HathiTrust)
Final environmental statement related to selection of the preferred closed cycle cooling system at Indian Point Unit no. 3. (U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation :, 1979), by U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation (page images at HathiTrust)
Thermal performance and water utilization measurement on ultimate heat sinks - cooling ponds and spray ponds (The Commission :, 1981), by R. K. Hadlock, O. B. Abbey, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Staff report on the generic assessment of feedwater transients in pressurized water reactors designed by the Babcock & Wilcox Company (Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation ;, 1979), by U.S. Nuclear Regulatory Commission. Division of Systems Safety, U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation, and U.S. Nuclear Regulatory Commission. Division of Operating Reactors (page images at HathiTrust)
Bubble behavior in LMFBR core disruptive accidents : annual report October, 1977-September, 1978 (The Commission ;, 1979), by C. A. Erdman, University of Virginia. Department of Nuclear Engineering and Engineering Physics, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Evaluation of mathematical models for characterizing plume behavior from cooling towers (The Commission :, 1980), by Anthony Joseph Policastro, Fuel Cycle U.S. Nuclear Regulatory Commission. Division of Safeguards, University of Illinois at Urbana-Champaign. Department of Mechanical and Industrial Engineering, and Argonne National Laboratory. Division of Environmental Impact Studies (page images at HathiTrust)
BWR refill-reflood program task 4.3-single heated bundle experimental task plan (The Commission :, 1981), by D. D. Jones, J. A. Findlay, L. L. Myers, General Electric Company. Nuclear Engineering Division, Electric Power Research Institute, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Identification of new unresolved safety issues relating to nuclear power plants : special report to Congress (Division of Safety Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission :, 1981), by U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Safety Technology (page images at HathiTrust)
Bubble behavior in LMFBR core disruptive accidents : annual report, July 1, 1976 - September 30, 1977 (Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commision ;, 1978), by Albert B. Reynolds, C. A. Erdman, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and University of Virginia. Department of Nuclear Engineering (page images at HathiTrust)
Bubble behavior in LMFBR core disruptive accidents : annual report, October 1979 - September 1980 (Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission :, 1981), by Albert B. Reynolds, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation, and University of Virginia. Department of Nuclear Engineering and Engineering Physics (page images at HathiTrust)
Development of a side-scatter gamma ray system for the measurement of local void fraction (The Division, 1979), by Susanne L. Schell, Richard T. Lahey, Rodney R. Gay, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Rensselaer Polytechnic Institute. Department of Nuclear Engineering (page images at HathiTrust)
A probabilistic safety analysis of DC power supply requirements for nuclear power plants (Division of Systems and Reliability Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission :, 1981), by P. W. Baranowsky, M. A. Fedele, Alan M. Kolaczkowski, U.S. Nuclear Regulatory Commission. Division of Systems and Reliability Research, Inc Evaluation Associates, and Sandia National Laboratories (page images at HathiTrust)
Multiloop Integral System Test (MIST) : final report (Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission :, 1989), by G. O. Geissler, J. R. Gloudemans, Babcock & Wilcox Owners Group, Electric Power Research Institute, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research, Babcock & Wilcox Company. Alliance Research Center, and Babcock & Wilcox Company. Nuclear Power Division (page images at HathiTrust)
ECC-bypass scaling (Nuclear Regulatory Commission, Division of Reactor Safety Research ;, 1979), by H. J. Richter, Graham B. Wallis, Thayer School of Engineering, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Summary report of pressure sensor for the loss of fluid test (LOFT) reactor (The Division, 1981), by T. R. Billeter, Hanford Engineering Development Laboratory, and Fuel Cycle U.S. Nuclear Regulatory Commission. Division of Safeguards (page images at HathiTrust)
Simulation experiments on two-phase natural circulation in a Freon-113 flow visualization loop (The Commission, 1988), by S. Y. Lee, M. Ishii, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
Nuclear reactor heat transfer (Argonne National Laboratory, 1961), by Paul A. Lottes, U.S. Atomic Energy Commission, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust)
Radioactivity of nuclear reactor cooling fluids (Oak Ridge National Laboratory, 1961), by John Clayton Ward and U.S. Atomic Energy Commission (page images at HathiTrust)
Analysis of the transient conduction of heat in long solid cylindrical fuel elements for nuclear reactors (Hanford Atomic Products Operation, 1956), by Frank Eugene Tippets, United States. Energy Research and Development Administration, and U.S. Atomic Energy Commission (page images at HathiTrust)
Boiling burnout experiments with 19-rod bundles in axial flow (U.S. Atomic Energy Commission, 1963), by J. M. Batch, D. E. Fitzsimmons, G. M. Hesson, E. D. Waters, 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. Reactor and Fuels Laboratory (page images at HathiTrust)
Examination of an irradiated, zircaloy-2, hot water loop tube (U.S. Atomic Energy Commission, 1960), by A. L. Bement, 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. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
High flow rate operation of a duplex ion exchange system (U.S. Atomic Energy Commission, 1960), by T. F. Demmitt, 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, Hanford Atomic Products Operation. Reactor and Fuels Research and Development Operation, and Hanford Atomic Products Operation (page images at HathiTrust)
Effect of wire wraps on pressure drop for axial turbulent flow through rod bundels (U.S. Atomic Energy Commission, 1963), by E. D. Waters, 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 study of radionuclide adsorption in the K recirculation loops (U.S. Atomic Energy Commission, 1961), by L. D. Perrigo, 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. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
Reactions of graphite with microwave-activated nitrogen : preliminary report (U.S. Atomic Energy Commission, 1961), by R. C. Giberson, 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. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
Experimental evaluation of the combustion hazard to the experimental gas-cooled reactor-preliminary burning rig experiments (U.S. Atomic Energy Commission, 1961), by R. E. Dahl, 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)
Plutonium recycle test reactor gas loop analysis (U.S. Atomic Energy Commission, 1961), by W. D. Cameron, 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)
High temperature, high pressure nozzle-to-tube connections for the 1706 KER facility (U.S. Atomic Energy Commission, 1957), by D. R. Doman, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
Irradiation of organic reactor coolants in dynamic systems (U.S. Atomic Energy Commission, 1957), by D. R. de Halas, U.S. Atomic Energy Commission, United States. Energy Research and Development Administration, Hanford Works, and Hanford Atomic Products Operation. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
Pyrolytic and radiolytic decomposition of organic reactor coolants (U.S. Atomic Energy Commission, 1957), by D. R. de Halas, 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. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
Irradiation of the biphenyl, ortho-, meta-terphenyl eutectic (U.S. Atomic Energy Commission, 1958), by D. R. de Halas, 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. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
Water loss rates following a piping failure in the PRTR (U.S. Atomic Energy Commission, 1960), by T. W. Ambrose, 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. Reactor and Fuels Research and Development Operation (page images at HathiTrust)
Proposed helium purification system for the experimental gas-cooled reactor (EGCR) (Oak Ridge National Laboratory, 1959), by F. A. Anderson, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Reactor Projects 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)
Low cost organic moderator-coolants for nuclear reactors (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by L. E. Gardner, J. C. Hillyer, W. M. Hutchinson, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
Hydraulics of modified fuel elements for engineering test reactor (U.S. Atomic Energy Commission, Idaho Operations Office, 1958), by R. G. Beck and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
Engineering test reactor core hydraulics (U.S. Atomic Energy Commission, Idaho Operations Office, 1958), by R. G. Beck, J. H. Rainwater, E. S. Brown, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
Reclamation of damaged nuclear reactor coolant by catalytic hydrocracking (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by L. E. Gardner, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Research and Development Department (page images at HathiTrust)
Evaluation of catalysts for selective hydrocracking of polyphenyls (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by L. E. Gardner, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Research and Development Department (page images at HathiTrust)
Catalytic hydrocracking of high boiler in nuclear reactor coolant (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by L. E. Gardner, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Research and Development Department (page images at HathiTrust)
Materials technology for an advanced space power nuclear reactor concept : program summary (National Aeronautics and Space Administration ;, 1975), by Richard E. Gluyas, Gordon K. Watson, and Lewis Research Center (page images at HathiTrust)
The Los Alamos homogeneous reactor, supo model (U.S. Atomic Energy Commission, Technical Information Service, 1952), by L. D. P. King, Los Alamos Scientific Labortory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Package power reactor no.1 : primary coolant system calculations (U.S. Atomic Energy Commission, Technical Information Service, 1953), by W. R. Gall, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Summary evaluation of organics as reactor moderator-coolants (United States Atomic Energy Commission, Technical Information Service ;, 1955), by R. O. Bolt, J. G. Carroll, U.S. Atomic Energy Commission, and California Research Corporation (page images at HathiTrust)
Natural convection cooling of liquid homogenous reactors (United States Atomic Energy Commission, Technical Information Service, 1949), by Howard Schwartz, North American Aviation, and U.S. Atomic Energy Commission (page images at HathiTrust)
Report on the engineering tests made in conjunction with the design of the Brookhaven Nuclear Reactor (Brookhaven National Laboratory, 1949), by W. E. Winsche, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
On the variation of [eta] with energy (Brookhaven National Laboratory, 1949), by E. P. Wigner, W. E. Winsche, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Water-spray cooling of air-cooled piles : an outline of problems encountered and possible solutions (United States Atomic Energy Commission, Technical Information Service, 1956), by Melville Clark, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Experimental studies on high-gravity rotating fluidized beds (Brookhaven National Laboratory, 1966), by G. C. Lindauer, L. P. Hatch, P. Tichler, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Random and ordered packing of spheres (Brookhaven National Laboratory, 1966), by H. Susskind, W. Becker, W. E. Winsche, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Controlled removal of spheres from an ordered packed bed by hydraulic means (Brookhaven National Laboratory, 1966), by Brookhaven National Laboratory and U.S. Atomic Energy Commission (page images at HathiTrust)
Pressure drop in geometrically ordered packed beds of spheres (Brookhaven National Laboratory, 1966), by H. Susskind, W. Becker, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Zirconium concentration measurements in the PRTR primary coolant : interim report, December 8, 1962 - June 30, 1963 (U.S. Atomic Energy Commission, 1963), by T. F. Demmitt, Hanford Works, and Hanford Atomic Products Operation (page images at HathiTrust)
Organic coolant research summary report : July 1, 1960 - March 31, 1963 (U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by J. C. Hillyer, Idaho National Reactor Testing Station, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust)
First semi-annual progress report on organic coolant technology (United States Atomic Energy, Division of Technical Information, 1962), by J. F. Black, P. R. Geissler, M. E. Conn, Esso Research and Engineering Company. Products Research Division, and U.S. Atomic Energy Commission. Division of Technical Information (page images at HathiTrust)
A brief description of a one megawatt convection cooled homogeneous reactor - Lapre II (Los Alamos Scientific Laboratory, 1955), by L. D. P. King and U.S. Atomic Energy Commission (page images at HathiTrust)
Gallium in nuclear reactors : considerations for use as a primary coolant (U.S. Atomic Energy Commission, Technical Information Service, 1952), by Robert Isaac Jaffee, B. W. Gonser, E. A. Fromm, R. M. Evans, Battelle Memorial Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
Nuclear reactor conversion design criteria process and control, secondary cooling system (Hanford Atomic Products Operation, 1963), by Hanford Atomic Products Operation and U.S. Atomic Energy Commission (page images at HathiTrust)
Performance criteria for irradiation processing department production reactors (Hanford Atomic Products Operation, 1963), by F. W. Van Wormer, General Electric Company, Hanford Atomic Products Operation, and U.S. Atomic Energy Commission (page images at HathiTrust)
Engineering audit of N-reactor's emergency cooling water system (Hanford Atomic Products Operation, 1964), by H. G. Johnson, General Electric Company, Hanford Atomic Products Operation, and U.S. Atomic Energy Commission (page images at HathiTrust)
Freon cascade refrigerator for liquid air plant precooler (Los Alamos Scientific Laboratory of the University of California, 1953), by William Ball, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
A brief description of a one megawatt convection cooled homogeneous reactor - Lapre II (U.S. Atomic Energy Commission, Technical Information Service, 1955), by L. D. P. King, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Analysis of water activation and component shielding for the ORNL package reactor power plant (United States Atomic Energy Commission, Technical Information Service Extension, 1957), by W. R. Pearce, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory (page images at HathiTrust)
Homogeneous Reactor Test cooler design data (United States Atomic Energy Commission, Technical Information Service ;, 1955), by R. G. Pitkin, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Externally cooled liquid metal fuel reactor : a reference design for low cost power (Available from the Office of Technical Services, U.S. Dept. of Commerce, 1960), by U.S. Atomic Energy Commission and Babcock & Wilcox Company (page images at HathiTrust)
Immiscible-liquid-cooled, fluid-fuel reactor (United States Atomic Energy Commission, Technical Information Service Extension ;, 1956), by W. D. Burch, Oak Ridge School of Reactor Technology, 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)
Studies of flow and mixing in a 0.4-scale model of the PWR Core 2 reactor (Battelle Memorial Institute, 1962), by Lawrence J. Flanigan, Herbert R. Hazard, Gale R. Whitacre, Battelle Memorial Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
Interim report on Scoping Emergency Cooling Heat Transfer Series I and II (U.S. Atomic Energy Commission, Idaho Operations Office, 1968), by L. G. Schlenker, W. S. Little, C. M. Moser, Idaho National Reactor Testing Station, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
Parametric studies of fuel pin temperature response (U.S. Atomic Energy Commission, Idaho Operations Office, 1969), by S. E. Jensen, Idaho National Reactor Testing Station, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust)
Suggestions on the design of heterogeneous reactors (Los Alamos Scientific Laboratory of the University of California, 1957), by Bob E. Watt, U.S. Atomic Energy Commission, and Los Alamos Scientific Laboratory (page images at HathiTrust)
Gas-suspension coolant project, final report (Office of Technical Information Extension, 1959), by U.S. Atomic Energy Commission and Babcock & Wilcox Company. Atomic Energy Division (page images at HathiTrust; US access only)
A preliminary evaluation of gas cooling of power reactors moderated by heavy water (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, 1958), by R. C. Holmes, E. W. Hones, L. Bernath, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
Heat flux at burnout (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1959), by Samuel Mirshak, R. H. Towell, William S. Durant, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
Leakage of water from gasketed joints proposed for the heavy water components test reactor (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1959), by William S. Durant, Samuel Mirshak, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
Thermal behavior of countercurrent equipment (E.I. du Pont de Nemours & Company, Explosives Department, Atomic Energy Divison, 1954), by Harold L. Hull, Herbert A. Pohl, U.S. Atomic Energy Commission, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
Heat flux at burnout in stagnant water (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1957), by Samuel Mirshak, Louis John Abate, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
Deposition of matter from a flowing stream. Part I, General relations and equations (U.S. Atomic Energy Commission, Division of Technical Information, 1962), by Leo F. Epstein, T. F. Evans, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Deposition of matter from a flowing stream. Part II, Application to a radioactive superheated stream system (U.S. Atomic Energy Commission, Division of Technical Information, 1962), by T. F. Evans, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Sulfur-cooled power reactor study : final report (Office Technical Information, U.S. Dept. of Energy, 1960), by D.R. Sawle, U.S. Atomic Energy Commission, Aerojet-General Corporation, and U.S. Atomic Energy Commission. Division of Technical Information (page images at HathiTrust)
Thermal warping of graphite pile (U.S. Atomic Energy Commission, Technical Information Service ;, 1943), by S. G. Bankoff, G. Rosner, C. P. Cabell, United States. Office of Scientific Research and Development. Metallurgical Laboratory, and U.S. Atomic Energy Commission. Technical Information Service (page images at HathiTrust)
Physical constants of proposed coolants (United States Atomic Energy Commission, Technical Information Service Extension ;, 1945), by Robert Bentley, Richard Schlegel, George Brown, United States. Office of Scientific Research and Development. Metallurgical Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
Effects of radiation on metal-clad graphite in high-temperature, high-pressure CO₂ (Technical Services, Department of Commerce ;, 1959), by W. L. Kosiba, United States Maritime Administration, U.S. Atomic Energy Commission, and General Dynamics Corporation. General Atomic Division (page images at HathiTrust)
Tests on half-scale flow model of 40-MW(E) prototype HTGR (Peach Bottom Atomic Power Station) (General Atomic Division of General Dynamics Corporation ;, 1962), by S. Ross, R. A. Skeehan, E. A. Day, General Dynamics Corporation. General Atomic Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
Bonus reactor superheater fuel emergency cooling : terminal report under BONUS activity no. 66-7 (United States Atomic Energy Commission, Division of Technical Information ;, 1960), by General Dynamics Corporation. General Atomic Division, General Nuclear Engineering Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
Statistical study of subcooled burnout including the effects of local hot spots (Knolls Atomic Power Laboratory, General Electric Company, 1957), by J. Longo, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust; US access only)
An evaluation of alternate coolant fast breeder reactors ([Atomic Energy Commission], 1969), by United States. Alternate Coolant Task Force and U.S. Atomic Energy Commission. Division of Reactor Development and Technology (page images at HathiTrust)
Advanced organic moderated reactor coolant screening and boiling test loops (Atomics International, 1960), by J. E. Leary, D. A. Huber, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
Piqua organic moderated reactor purification system development (Atomics International, 1960), by W. N. Bley, R. W. Burkhardt, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
Development of a variable orifice for Hallam Nuclear Power Facility fuel channels (Atomics International, 1961), by C. J. Baroczy, W. D. Leonard, J. A. Hagel, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
Design and construction of the Organic Moderated Reactor Experiment particulate removal loop (Atomics International, 1961), by H. Cataldo, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
Power and flow ramp stability tests on the sodium reactor experiment (Atomics International, 1962), by C. W. Griffin, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
Development of the pyrolytic fouling test for organic reactor coolants (Canoga Park, California : Atomics International, 1962., 1962), by P. R. Benson, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
Critical heat flux of some polyphenyl coolants (Canoga Park, California : Atomics International, 1963., 1963), by J. M. Robinson, H. Lurie, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
A survey of the decomposition rates of organic reactor coolants (Atomics International, 1959), by R. H. J. Gercke, C. A. Trilling, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
Flow stability test loop (Canoga Park, California : Atomics International, 1964., 1964), by F. Bergonzoli, F.J. Halfen, E. E. Stoner, W. H. Wickes, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
The irradiation of Santowax OMP in the M.I.T. in-pile loop Part I, Summary to October 5, 1961 (Massachusetts Institute of Technology, Deptartment of Nuclear Engineering, 1962), by Dean T. Morgan, Edward A. Mason, U.S. Atomic Energy Commission. Idaho Operations Office, and Massachusetts Institute of Technology. Department of Nuclear Engineering (page images at HathiTrust)
Organic in-pile loop : NAA-18 (Atomics International, 1956), by S. Nakazato, R. H. J. Gercke, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
Experimental determination of contaminants in sodium (Washington, D.C. : Department of Commerce, Office of Technical Services, 1961., 1961), by H. Steinmetz, B. Minushkin, United Nuclear Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
Transient hydrodynamic operation of EGCR main coolant system (Oak Ridge Gaseous Diffusion Plant, Union Carbide Nuclear Company, 1961), by D. W. Burton, Union Carbide Nuclear Company. Oak Ridge Gaseous Diffusion Plant, U.S. Atomic Energy Commission, and Oak Ridge Gaseous Diffusion Plant (page images at HathiTrust)
Petroleum refinery streams as prospective reactor coolants : thermal stability investigations (Oak Ridge, Tennessee : U.S. Atomic Energy Commission, Office of Technical Information Extension, 1960., 1960), by J. G. Carroll, U.S. Atomic Energy Commission, and California Research Corporation (page images at HathiTrust)
Economics of the use of surface condensers with dry-type cooling systems for fossil-fueled and nuclear generating plants (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1973., 1973), by John Paul Rossie, Max E. Kiburz, Rodger O. Young, Robert D. Mitchell, U.S. Atomic Energy Commission. Division of Reactor Research and Development, and R.W. Beck and Associates (page images at HathiTrust)
Cost comparison of dry-type and conventional cooling systems for representative nuclear generating plants (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1972., 1972), by John Paul Rossie, Rodger O. Young, Edward A. Cecil, U.S. Atomic Energy Commission. Division of Reactor Development and Technology, and R.W. Beck and Associates (page images at HathiTrust)
Survey of coolant vaporization effects important to fast reactor safety (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1962., 1962), by Arthur J. Goldman, U.S. Atomic Energy Commission, and United Nuclear Corporation (page images at HathiTrust)
Investigation of wet steam as a reactor coolant (CAN-2) (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1962., 1962), by A. Weinstein, F. Nakache, G. Sofer, M. Raber, S. Israel, Mark Crane, R. Hankel, H. Firstenberg, R. P. Stein, U.S. Atomic Energy Commission, and United Nuclear Corporation (page images at HathiTrust)
Investigation of burnout heat flux in rectangular channels at 2000 psia (Oak Ridge, Tennessee : U.S. Atomic Energy Commission, Technical Information Service Extension, 1955., 1955), by H. S. Jacket, J. E. Zerbe, J. D. Roarty, Westinghouse Electric Corporation, Bettis Atomic Power Laboratory, and U.S. Atomic Energy Commission. Technical Information Service Extension (page images at HathiTrust)
Zirconium-water reaction data and application to PWR loss-of-coolant accident (Washington, D.C. : Office of Technical Services, Department of Commerce, 1957., 1957), by Benjamin Lustman, U.S. Atomic Energy Commission, Bettis Atomic Power Laboratory, and Westinghouse Electric Corporation (page images at HathiTrust)
Basic properties of ice as related to the performance of ice condensers ([Washington, D.C.] : U.S. Atomic Energy Commission, Directorate of Licensing : For sale by the Supt. of Docs., U.S. G.P.O., 1972., 1972), by B. A. Soldano, Furman University, and U.S. Atomic Energy Commission Directorate of Licensing (page images at HathiTrust)
Potential for low fracture toughness and lamellar tearing on PWR steam generator and reactor coolant pump supports : resolution of generic technical activity A-12 (Washington, D.C. : Division of Operating Reactors, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1979., 1979), by J. J. Zudans, H. A. Levin, J. M. Hodge, R. P. Snaider, and U.S. Nuclear Regulatory Commission. Division of Operating Reactors (page images at HathiTrust)
Unresolved safety issues : pressurized thermal shock : oversight hearing before the Subcommittee on Oversight and Investigations of the Committee on Interior and Insular Affairs, House of Representatives, Ninety-seventh Congress, second session, on unresolved safety issues, pressurized thermal shock; hearing held in Washington, D.C., May 7, 1983. (U.S. G.P.O, 1984), by United States. Congress. House. Committee on Interior and Insular Affairs. Subcommittee on Oversight and Investigations (page images at HathiTrust)
Atomic energy, thermal-hydraulic transients program and emergency core cooling systems-reflood program : agreement between the United States of America and Switzerland, amending and extending the agreement of June 15 and July 9, 1979, signed at Bethesda and Bern, March 27 and May 2, 1984. (Dept. of State :, 1991), by Switzerland, United States. 1979 June 15. 1984 March 27, and United States Department of State (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)
The passive response of a metal fueled pool-type reactor to the chilled inlet accident (Argonne, Illinois : Argonne National Laboratory, Chemical Technology Division, 1993., 1993), by R. B. Vilim, University of Chicago, and Argonne National Laboratory (page images at HathiTrust)
Sudden loss of flow in an integral fast reactor (Argonne, Illinois : Argonne National Laboratory, Reactor Analysis Division, 1993., 1993), by R. H. Sevy, University of Chicago, and Argonne National Laboratory (page images at HathiTrust)
ALMR MOD A RVACS sensitivity to wind effects via wind tunnel modeling (Argonne, Illinois : Argonne National Laboratory, Reactor Engineering Division, 1993., 1993), by B. Bonomo, W. H. Gunther, University of Chicago, and Argonne National Laboratory (page images at HathiTrust)
Reactor Development Program Progress Report. : December 1961 (Argonne National Laboratory, 1962), by Albert V. Crewe and Argonne National Laboratory (page images at HathiTrust)
Conceptual design and economic evaluation of a steam-cooled fast breeder reactor (United Nuclear Corporation, Development Division, 1961), by G. Sofer, United Nuclear Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
Reactor Development Program Progress Report. : December 1964 (Argonne National Laboratory, 1965), by Albert V. Crewe and Argonne National Laboratory (page images at HathiTrust)
Thermal hydraulic performance characteristics of EBWR (o to 100 Mwt) (Argonne National Laboratory, Reactor Engineering Division, 1963), by Michael Petrick, E. A. Spleha, and Argonne National Laboratory (page images at HathiTrust)
Reactor Development Program Progress Report. : December 1962 (Argonne National Laboratory, 1963), by Albert V. Crewe and Argonne National Laboratory (page images at HathiTrust)
Proceedings of the AMU-ANL Summer Study Program. : June 19 - Jul 14, 1961. (Argonne National Laboratory, Industrial Hygiene and Safety Division, 1962), by Argonne National Laboratory (page images at HathiTrust)
Boiling water reactor technology status of the art report : Volume 1. Heat transfer and hydraulics (Argonne National Laboratory, Reactor Engineering Division, 1962), by P. A. Lottes 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)
Advanced test reactor burnout heat transfer tests (Babcock & Wilcox Co., 1964), by M. W. Croft, U.S. Atomic Energy Commission. Idaho Operations Office, U.S. Atomic Energy Commission. Division of Technical Information, and Babcock & Wilcox Company (page images at HathiTrust)
Maintenance of engineering test reactor coolant (Idaho Operations Office, U.S. Atomic Energy Commission, 1958), by F. C. Haas, Phillips Petroleum Company. Atomic Energy Division, and U.S. Atomic Energy Commission. Idaho Operations Office (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)
Design of the Argonne Low Power Reactor (ALPR) (Argonne National Laboratory, Reactor Engineering Division, 1961), by Eberhard E. Hamer and Argonne National Laboratory (page images at HathiTrust)
Axial heat distribution in Brookhaven reactor (United States Atomic Energy Commission, Technical Information Service, 1955), by Melville Clark, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
The transient behavior of single-phase natural circulation water loop systems (Argonne National Laboratory, 1956), by C. D. Alstad and Argonne National Laboratory (page images at HathiTrust)
Special Power Excursion Reactor Tests III pressurizer vessel failure (Idaho Operations Office, U.S. Atomic Energy Commission, 1962), by K. R. Hoopingarner, W. W. Hickman, D. P. Halls, T. R. Wilson, R. E. Heffner, Phillips Petroleum Company. Atomic Energy Division, U.S. Atomic Energy Commission. Idaho Operations Office, and Idaho National Reactor Testing Station (page images at HathiTrust)
Reactor Development Program Progress Report. : May 1965 (Argonne National Laboratory, 1965), by Albert V. Crewe and Argonne National Laboratory (page images at HathiTrust)
Reactor Development Program Progress Report. : December 1963 (Argonne National Laboratory, 1964), by Albert V. Crewe and Argonne National Laboratory (page images at HathiTrust)
Reactor Development Program Progress Report. : December 1960 (Argonne National Laboratory, 1961), by N. Hilberry and Argonne National Laboratory (page images at HathiTrust)
Reactor Development Program Progress Report. : November 1964 (Argonne National Laboratory, 1964), by Albert V. Crewe and Argonne National Laboratory (page images at HathiTrust)
Reactor Development Program Progress Report. : April 1963 (Argonne National Laboratory, 1963), by Albert V. Crewe and Argonne National Laboratory (page images at HathiTrust)
Reactor Development Program Progress Report. : March 1961 (Argonne National Laboratory, 1961), by N. Hilberry and Argonne National Laboratory (page images at HathiTrust)
In-pile loop irradiation studies of organic coolant materials : progress report, January 1- September 30, 1965 (Cambridge, Massachusetts : Massachusetts Institute of Technology, Department of Nuclear Engineering, 1965., 1965), by Dean T. Morgan, Thomas Howard Timmins, W. N. Bley, U.S. Atomic Energy Commission. Savannah River Operations Office, U.S. Atomic Energy Commission, and Massachusetts Institute of Technology. Department of Nuclear Engineering (page images at HathiTrust)
Toxicological studies on polyphenyl compounds used as atomic reactor moderator-coolants (West Los Angeles, California : University of California, Department of Nuclear Medicine and Radiation Biology, 1959., 1959), by Thomas J. Haley, L. Baurmash, H. C. Upham, P. Williams, N. Komesu, L. E. Detrick, Los Angeles University of California, and U.S. Atomic Energy Commission (page images at HathiTrust)
Boiling pressure drop in rectangular channels (Pittsburgh, Pennsylvania. : Atomic Power Division, Westinghouse Electric Corporation, 1956., 1956), by H. S. Jacket, N. C. Sher, J. D. Roarty, U.S. Atomic Energy Commission, and Westinghouse Electric Corporation. Atomic Power Division (page images at HathiTrust)
Coolant mixing in sodium cooled fast reactor fuel bundles (Washington, D.C. : U.S. Atomic Energy Commission, Division of Reactor Development and Technology, 1968., 1968), by Neil E. Todreas, L. W. Wilson, and U.S. Atomic Energy Commission. Division of Reactor Development and Technology (page images at HathiTrust)
B.W.R. blowdown/emergency core cooling, seventeenth quarterly progress report, January 1 - March 31, 1980 (Washington, D.C. : United States Nuclear Regulatory Commission and Electric Power Research Institute, 1981., 1981), by L. S. Lee, General Electric Company. Nuclear Engineering Division, Electric Power Research Institute, U.S. Nuclear Regulatory Commission, United States Government Printing Office, and United States. National Technical Information Service (page images at HathiTrust)
B.W.R. blowdown/emergency core cooling, eighteenth quarterly progress report, April 1 - June 30, 1980 (Washington, D.C. : United States Nuclear Regulatory Commission and Electric Power Research Institute, 1980., 1980), by W. S. Hwang, General Electric Company. Nuclear Engineering Division, Electric Power Research Institute, U.S. Nuclear Regulatory Commission, United States Government Printing Office, and United States. National Technical Information Service (page images at HathiTrust)
B.W.R. refill-reflood program task 4.3 - single heated bundle experimental task plan (Washington, D. C. : Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission and Electric Power Research Institute and Nuclear Engineering Division, General Electric Company, 1981., 1981), by D. D. Jones, United States. National Technical Information Service, United States Government Printing Office, General Electric Company. Nuclear Engineering Division, Electric Power Research Institute, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
Examination of failed studs from no. 2 steam generator at the Maine Yankee Nuclear Power Station (Washington, D. C. : U.S. Nuclear Regulatory Commission, 1983., 1983), by C. Czajkowski, Brookhaven National Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering (page images at HathiTrust)
Modification of O.C.A.-I. for application to a reactor pressure vessel with cladding on the inner surface (Washington, D. C. : U.S. Nuclear Regulatory Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission, 1983., 1983), by A. Sauter, S. K. Iskander, R. D. Cheverton, Oak Ridge National Laboratory. Engineering Technology Division, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research (page images at HathiTrust)
Reactor development program progress report December 1968 (Argonne, Illinois. : Argonne National Laboratory, 1969., 1969), by Robert B. Duffield, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
Investigation of the use aqueous solutions as emergency coolants : final report (Dunedin, Florida : Southern Nuclear Engineering, Inc., 1969., 1969), by C. Rogers McCullough, S. E. Turner, R. P. Hancock, Gilbert M. Brown, U.S. Atomic Energy Commission, and Inc Southern Nuclear Engineering (page images at HathiTrust)
Fission product behavior under simulated loss-of-collant accident conditions in the contamination-decontamination experiment (Idaho Falls, Idaho : Idaho Nuclear Corporation, National Reactor Testing Station, 1969., 1969), by W. A. Freeby, D. E. Black, L. T. Lakey, U.S. Atomic Energy Commission. Idaho Operations Office, Allied Chemical Corporation, and Aerojet-General Corporation (page images at HathiTrust)
Development of testing procedures for protective coatings to be used in nuclear reactor containment structures (Idaho Falls, Idaho : Idaho Nuclear Corporation, National Reactor Testing Station, 1969., 1969), by B. J. Newby, W. T. Jordan, K. L. Rohde, U.S. Atomic Energy Commission. Idaho Operations Office, Allied Chemical Corporation, and Aerojet-General Corporation (page images at HathiTrust)
Removal of chromates from process cooling water by the reduction and precipitation process (Paducah, Kentucky. : Union Carbide Corporation, Nuclear Division, Paducah Gaseous Diffusion Plant , 1972., 1972), by E. W Richardson and U.S. Atomic Energy Commission (page images at HathiTrust)
Natural convection cooling of liquid homogenous reactors (Los Angeles, California : North American Aviation, Inc., 1949., 1949), by Howard Schwartz, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)

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