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Filed under: Boiling water reactors -- Wisconsin -- Genoa La Crosse Boiling Water Reactor project: hearing before the Subcommittee on Legislation of the Joint Committee on Atomic Energy, Congress of the United States, Ninetieth Congress, first session, on La Crosse Boiling Water Reactor project and materials concerning Hallam Elk River, Pathfinder, BONUS, and Piqua reactor projects, May 4, 1967. (U.S. Govt. Print. Off., 1969), by United States. Congress. Joint Committee on Atomic Energy. Subcommittee on Legislation (page images at HathiTrust) Filed under: La Crosse Boiling Water Reactor (Genoa, Wis.) La Crosse Boiling Water Reactor project: hearing before the Subcommittee on Legislation of the Joint Committee on Atomic Energy, Congress of the United States, Ninetieth Congress, first session, on La Crosse Boiling Water Reactor project and materials concerning Hallam Elk River, Pathfinder, BONUS, and Piqua reactor projects, May 4, 1967. (U.S. Govt. Print. Off., 1969), by United States. Congress. Joint Committee on Atomic Energy. Subcommittee on Legislation (page images at HathiTrust)
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Filed under: Boiling water reactors Calculation of releases of radioactive materials in gaseous liquid effluents from boiling water reactors (BWR-GALE code) (Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Site Safety and Environmental Analysis, Effluent Treatment Systems Branch ;, 1979), by R. R. Bellamy, F. P. Cardile, R. L. Bangart, and U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Effluent Treatment Systems Branch (page images at HathiTrust) Report on BWR control rod drive mechanical failures : Technical Activity B-48 (Division of Operating Reactors, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission ;, 1979), by K. N. Jabbour and U.S. Nuclear Regulatory Commission. Division of Operating Reactors (page images at HathiTrust) Buckling criteria and application of criteria to design of steel containment shell : final report, January 1978 - March 1979 (Division of Systems Safety, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission;, 1979), by Paul Seide, S. F. Masri, V. Weingarten, U.S. Nuclear Regulatory Commission. Division of Systems Safety, and International Structural Engineers (page images at HathiTrust) Experimental boiling water reactor (EBWR) shield design (Argonne National Laboratory, 1956), by M. Grotenhuis and J. W. Butler (page images at HathiTrust) Dynamic analysis of natural circulation boiling water power reactors (Argonne National Laboratory, 1958), by Eric S. Beckjord (page images at HathiTrust) Experiments on boiling core B-2, BORAX-V (Argonne National Laboratory, 1964), by BORAX-V project staff (page images at HathiTrust) Lecture notes on heat extraction from boiling water power reactors (Argonne National Laboratory, 1959), by Paul A. Lottes, J. F. Marchaterre, and Michael Petrick (page images at HathiTrust) Performance characteristics of EBWR from 0 to 100 Mwt (Argonne National Laboratory, 1963), by H. Iskenderian, W. C. Lipinski, Michael Petrick, and E. A. Wimmunc (page images at HathiTrust) A study of heavy water central station boiling reactors (CSBR) (Argonne National Laboratory, 1958), by L. Link, B. Hoglund, M. Petrick, L. Templin, D. Shaftman, and M. Treshow (page images at HathiTrust) Analyses of experimental power-reactivity feedback transfer functions for a natural circulation boiling water reactor (Argonne National Laboratory, 1958), by J. A. DeShong, W. C. Lipinski, U.S. Atomic Energy Comission, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust) Dynamic behavior of boiling reactors (Argonne National Laboratory, 1959), by J. A. Thie, U.S. Atomic Energy Comission, and Argonne National Laboratory (page images at HathiTrust) Experimental Boiling Water Reactor turbine blade failure : summary report (Argonne National Laboratory, 1958), by J. M. Harrer, E. A. Wimunc, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust) An empirical modification of nucleation theory and its application to boiling heat transfer (Argonne National Laboratory, 1961), by Yan-Po Chang (page images at HathiTrust) Natural and forced-circulation boiling studies (Argonne National Laboratory, 1960), by W. S. Flinn, R. J. Weatherhead, P. A. Lottes, M. Petrick, and J. F. Marchaterre (page images at HathiTrust) Two-phase pressure drop in a natural-circulation boiling channel (Argonne National Laboratory, 1961), by B. M. Hoglund, T. R. Epperson, and R. J. Weatherhead (page images at HathiTrust) A gamma-ray attenuation method for void fraction determinations in experimental boiling heat transfer test facilities (Argonne National Laboratory, 1958), by H. H. Hooker and G. F. Popper (page images at HathiTrust) Design study of small boiling reactors for power and heat production (U.S. Atomic Energy Commission, 1957), by M. Treshow (page images at HathiTrust) Some steady-state thermal characteristics of a three-loop reactor power system (Reactor Engineering Division, Argonne National Laboratory, 1960), by T. R. Bump, H. O. Monson, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust) Water chemistry and fuel element scale in experimental boiling water reactor (Reactor Engineering Division, Argonne National Laboratory, 1960), by C. R. Breden, R. H. Leyse, I. Charak, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust) The internal feedback of EBR-I, Mark-III (Argonne National Laboratory, 1960), by J. C. Carter, J. H. Tessier, D. W. Sparks, Inc Land-Air, U.S. Atomic Energy Comission, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust) Metallurgical evaluation of failed BORAX-IV reactor fuel elements (Argonne National Laboratory, 1961), by J. H. Kittel, R. Carlander, L. A. Neĭmark, C. F. Reinke, and U.S. Atomic Energy Comission (page images at HathiTrust) Power-to-void transfer functions (Argonne National Laboratory, 1961), by Helge Christensen, U.S. Atomic Energy Comission, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust) The continuous monitoring of boric acid concentration by neutron absorptiometry (Argonne National Laboratory, 1961), by Roland J. Armani, U.S. Atomic Energy Comission, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust) High-temperature sensors for BORAX-V boilng fuel rods (Argonne National Laboratory, 1962), by E. J. Brooks, R. D. McGowan, W. C. Kramer, U.S. Atomic Energy Comission, Argonne National Laboratory. Metallurgy Division, and Argonne National Laboratory. Idaho Division (page images at HathiTrust) BORAX V exponential experiment (Argonne National Laboratory, 1963), by F. S. Kirn, J. I. Hagen, U.S. Atomic Energy Comission, and Argonne National Laboratory. Idaho Division (page images at HathiTrust) Zero-power experiments with boiling core B-1, BORAX-V (Argonne National Laboratory, 1964), by BORAX-V Project Staff and U.S. Atomic Energy Commission. Idaho Division (page images at HathiTrust) Boiling water reactor technology status of the art report. Volume II, Water chemistry and corrosion (Argonne National Laboratory, 1963), by C. R. Breden, U.S. Atomic Energy Comission, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust) Study of 40 megawatt pressurized water, boiling water, and organic moderated reactors for production of process steam (Argonne National Laboratory, 1959), by L. E. Link (page images at HathiTrust) Prototype boiling water reactor (Argonne National Laboratory, 1959), by J. M. Harrer (page images at HathiTrust) Tests of defected toria-urania fuel specimiens in Experimental Boiling Water Reactor (Argonne National Laboratory, 1960), by R. F. S. Robertson and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust) Examination of an irradiated prototype fuel element for the Elk River reactor (Argonne National Laboratory, 1961), by L. A. Neĭmark and Argonne National Laboratory. Metallurgy Division (page images at HathiTrust) Experimental boiling water reactor reactor pressure vessel revisions for instrumentation and increased steam output (Argonne National Laboratory, 1962), by T. L. Kettles, N. Balai, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust) The Zr2 - CaO - UO2 ceramic fuel fabrication for the EBWR spiked core elements (Argonne National Laboratory, 1961), by R. C. Lied, J. H. Handwerk, E. D. Lynch, and Argonne National Laboratory. Metallurgy Division (page images at HathiTrust) Physics analysis of proposals for Experimental Boiling Water Reactor core 2 (Argonne National Laboratory, 1961), by R. Avery, C. N. Kelber, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust) Experimental Boiling Water Reactor core 1A physics analyses (Argonne National Laboratory, 1961), by C. Kelber, H. Iskenderian, C. Carson, K. Almenas, R. Avery, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust) Experiments with central superheater core CSH-1, Boiling Reactor Experiment V (Argonne National Laboratory, 1965), by Argonne National Laboratory) BORAX-V Project Staff (Idaho Division and Argonne National Laboratory. Idaho Division (page images at HathiTrust) Homogenous and quasi-homogenous reactors (Argonne National Laboratory, 1964), by Charles E. Teeter, John H. Martens, James A. Lecky, and Argonne National Laboratory. Technical Publications Department (page images at HathiTrust) Modification of the experimental boiling water reactor (EBWR) for higher-power operation (Argonne National Laboratory, 1962), by J. F. Matousek and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust) A study of the variation of steam velocity in vertical boiling channels (Argonne National Laboratory, 1960), by General Nuclear Engineering Corporation (page images at HathiTrust) Terminal report on the boiling Slurry Reactor Experiment (SLURREX) : (mockup hydraulic experiments) (Argonne National Laboratory, 1961), by Joseph D. Lokay and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust) Experimental Boiling Water Reactor test reports (Argonne National Laboratory, 1960), by V. M. Kolba and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust) Removal of Experimental Boiling Water Reactor fuel element scale by slurry honing (Argonne National Laboratory, 1960), by Ira Charak and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust) Review of power and heat reactor designs : domestic and foreign (U.S. Atomic Energy Commission, 1963), by E. R. Appleby, Hanford Works, and Hanford Atomic Products Operation. Finance and Administration Operation (page images at HathiTrust) Review of power and heat reactor designs : domestic and foreign (U.S. Atomic Energy Commission, 1961), by E. R. Appleby, U.S. Atomic Energy Commission, Hanford Works, and Hanford Atomic Products Operation. Hanford Laboratories Operation (page images at HathiTrust) Water boiler (Atomic Energy Commission, 1947), by Los Alamos Scientific Laboratory and U.S. Atomic Energy Commission (page images at HathiTrust) Process for dissolution of Borax IV reactor fuel : laboratory development (Oak Ridge National Laboratory, 1960), by L. M. Ferris, U.S. Atomic Energy Commission, Union Carbide Corporation, and Oak Ridge National Laboratory. Chemical Technology Division. Chemical Development Section B. (page images at HathiTrust) Review and analysis of radwaste management for light water reactors (Cornell Energy Project, Center for Environmnetal Quality Management, Cornell University, 1972), by J. A. Franco and K. B. Cady (page images at HathiTrust; US access only) The SPERT III reactor nuclear startup (U.S. Atomic Energy Commission, Idaho Operations Office, 1960), by R. A. Zahn, C. R. Toole, W. J. Neal, F. Schroeder, and Phillips Petroleum Company. Atomic Energy Division (page images at HathiTrust) Analytical and experimental study of the dynamics of a single-tube counterflow boiler (National Aeronautics and Space Administration ;, 1969), by H. L. Hess, S. L. Organ, J. R. Hooper, United States National Aeronautics and Space Administration, Lewis Research Center, and United Aircraft Corporation (page images at HathiTrust) Further boiling experiments in the LITR (U.S. Atomic Energy Commission, Technical Information Service, 1955), by W. M. Breazeale, J. A. Cox, T. E. Cole, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust) A boiling point-composition diagram of the system uranyl nitrate-nitric acid-water (U.S. Atomic Energy Commission, Technical Information Service, 1954), by A. E. Ruehle, Mo.) Mallinckrodt Chemical Works (Saint Louis, and U.S. Atomic Energy Commission (page images at HathiTrust) Relative effectiveness of delayed neutrons in the waterboiler (U.S. Atomic Energy Commission, Technical Information Service, 1951), by F. de Hoffmann, Los Alamos Scientific Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust) Borax experiments, 1953 (U.S. Atomic Energy Commission, Technical Information Service, 1954), by Joseph R. Dietrich, D. C. Layman, Walter H. Zinn, and Argonne National Laboratory (page images at HathiTrust) Transient heat transfer in reactor coolant channels (Technical Information Service Extension, 1957), by Ralph P. Stein and U.S. Atomic Energy Commission (page images at HathiTrust) A space-independent model of two-phase flow and its application to experiment (Brookhaven National Laboratory, 1966), by Louis M. Shotkin, Brookhaven National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust) Argonne National Laboratory.. (U.S. Atomic Energy Commission, Technical Information Service Extension, 1956), by C. F. Bullinger, W. S. Flinn, S. A. Bernsen, C. K. Soppet, J. M. West, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust) The influence of pressure on boiling water reactor dynamic behavior at atomospheric pressure ([Lawrence] Radiation Laboratory, 1960), by Joseph A. Fleck, Lawrence Radiation Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust) Reactor physics of Teapot. Part II (U.S. Atomic Energy Commission, Technical Information Extension ;, 1955), by Paul R. Kasten, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory (page images at HathiTrust) Reactor governors (U.S. Atomic Energy Commission, Technical Information Service ;, 1955), by Paul R. Kasten, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory (page images at HathiTrust) A parametric study of rate of power removal from homogeneous boiling reactors (Oak Ridge National Laboratory, 1955), by L. G. Alexander, S. Jaye, and U.S. Atomic Energy Commission (page images at HathiTrust) Development of niobium-base alloys for use in a nuclear superheater (Battelle Memorial Institute ;, 1963), by Frank A. Rough, Arthur A. Bauer, Warren E. Berry, John A. DeMastry, Battelle Memorial Institute, and U.S. Atomic Energy Commission (page images at HathiTrust) Radionuclide release under specific LWR accident conditions : draft report (U.S. G.P.O., 1983), by J. A. Gieseke, Battelle Memorial Institute, U.S. Atomic Energy Commission, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research (page images at HathiTrust) Irradiation of a U - 2% Zr fuel tube in the Vallecitos Boiling Water Reactor (E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, 1962), by Henry C. Quigley, U.S. Atomic Energy Commission, and Savannah River Laboratory (page images at HathiTrust) Natural circulation loop performance at 1000 psia under periodic accelerations. Part I, Initial experimental results. Part II, Analog prediction of flow characteristics (United States Atomic Energy Commission, Office of Technical Information ;, 1960), by E. P. Quinn, J. M. Case, General Electric Company, and U.S. Atomic Energy Commission (page images at HathiTrust) The flux trap core for a marine boiling water reactor in the T7 tanker : summary design report (United States Atomic Energy Commission, Division of Technical Information ;, 1960), by J. R. Birle, Vallecitos Atomic Laboratory, General Electric Company, and U.S. Atomic Energy Commission (page images at HathiTrust) The stability of two-phase flow loops and response to ship's motion (Atomic Power Equipment Dept., GE, 1960), by E. S. Beckjord and General Electric Company. Atomic Power Equipment Department (page images at HathiTrust) Effects of vertical gravity oscillations on performance of the T7 natural circulation boiling water reactor (U.S. Atomic Energy Commission, Division of Technical Information, 1961), by G. R. Pflasterer, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust) Design and fabrication of high power density fuel assemblies for Vallecitos Boiling Water Reactor irradiation testing (United States Atomic Energy Commission, Office of Technical Information ;, 1960), by W. D. Fowler, J. W. Lingafelter, U.S. Atomic Energy Commission, and General Electric Company (page images at HathiTrust) Critical heat flux and flow pattern characteristics of high pressure boiling water in forced convection (U.S. Atomic Energy Commission, Division ofTechnical Information, 1962), by Frank Eugene Tippets, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust) Development of process tubes for nuclear superheat applications (U.S. Atomic Energy Commission, Division of Technical Informatio, 1961), by E. L. Esch, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust) AEC Superheat criticals : a comparison of experiment and theory on uniform lattices (General Electric Company, Atomic Power Equipment Dept., 1962), by G. T. Peteresen, F. G. Warzek, U.S. Atomic Energy Commission. Division of Technical Information, and General Electric Company. Atomic Power Equipment Department (page images at HathiTrust) 300 MWe High Power Density conceptual design study (United States Atomic Energy Commission, Division of Technical Information, 1962), by A. P. Bray, V. G. Grayhek, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust) Powder fuel processing by two-pass swaging : the effect of particle size and distribution (U.S. Atomic Energy Commission, Division of Technical Information, 1962), by C. M. Ryer, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust) Vallecitos Boiling Water Reactor irratiation of reactor control materials in tubes containing simulated defects (U.S. Atomic Energy Commission, Division of Technical Information, 1963), by Frederic Henry Megerth, D. L. Zimmerman, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust) 300 MWe High Power Density conceptual design study (United States Atomic Energy Commission, Division of Technical Information, 1962), by A. P. Bray, V. G. Grayhek, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust) Methods for improving the critical heat flux for Boiling Water Reactor's (U.S. Atomic Energy Commission, Division of Technical Information, 1963), by C. L. Howard, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust) Feasibility investigation of a closed cycle boiling water reactor for the propulsion of a merchant ship, addendum 1. (U.S. Atomic Energy Commission, Technical Information Service Extension, 1957), by U.S. Atomic Energy Commission, U.S. Atomic Energy Commission. Technical Information Service, Nuclear Engineering Laboratory (American Machine and Foundry Co.), United States. Maritime Administration. Office of Nuclear Projects, and American Machine and Foundry Company (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) Insulation and seal connector development (United States Atomic Energy Commission, Division of Technical Information ;, 1961), by General Dynamics Corporation. General Atomic Division, General Nuclear Engineering Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust) Study of a boiling reactor steam plant for central station power (United States Atomic Energy Commission, Technical Information Service, 1954), by J. W. Weil, T. M. Snyder, E. L. Zebroski, Knolls Atomic Power Laboratory, General Electric Company, and U.S. Atomic Energy Commission (page images at HathiTrust) Boiling water reactor plant. (For sale by the Superintendent of Documents, U.S. Govt. Print Off, 1972), by inc United Engineers & Constructors and U.S. Atomic Energy Commission. Division of Reactor Development and Technology (page images at HathiTrust) The development of linear power detection and recording instrument systems for the kinetic experiments on water boilers (Canoga Park, California : Atomics International, 1963., 1963), by E. L. Gardner, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust) Summary review of the kinetics experiments on water boilers (Canoga Park, California : Atomics International, 1963., 1963), by M. S. Dunenfeld, R. K. Stitt, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust) Comparative fuel cycle evaluations low decontamination pyroprocessing vs. aqueous reprocessing. Part 1, UOb2s fuel in a thermal reactor (Canoga Park, California : Atomics International, 1963., 1963), by L. J. Colby, Walther Stoltzing, E. W. Murbach, H. Pearlman, K. L. Mattern, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust) Investigation of reactor transients and power patterns of a heavy water-moderated, boiling heavy water-cooled reactor (Washington, D.C. : Department of Commerce, Office of Technical Services, 1961., 1961), by C. Graves, C. Marotta, H. G. Elrod, L. Berkowitz, F.E. Beers, Nuclear Development Corporation of America, and U.S. Atomic Energy Commission (page images at HathiTrust) Boiling nuclear superheater (BONUS) power station; preliminary design study and hazards summary report. (U.S. Atomic Energy Commission, Technical Information Service], 1960), by Puerto Rico. Water Resources Authority and General Nuclear Engineering Corporation (page images at HathiTrust) Boiling water reactor technology status of the art report / [edited by C. Victor Pearson]. (Reactor Engineering Division, Argonne National Laboratory, 1962), by C. Victor Pearson and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust) Theory of small oscillations in boiling water nuclear reactors (Los Angeles, California : Ramo-Wooldridge Corporation, Electronic Research Laboratory ; Washington, D.C. : Available from the Office of Technical Services, Deptartment of Commerce, 1958., 1958), by H. C. Corben, R. S. Margulies, David B. Langmuir, Ramo-Wooldridge Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust) Boiling water reactors : an annotated bibliography of selected literature (Oak Ridge, Tennessee : U.S. Atomic Energy Commission, Technical Information Service, 1959., 1959), by James M. Jacobs and U.S. Atomic Energy Commission (page images at HathiTrust) Boiling water reactor program (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1957., 1957), by U.S. Atomic Energy Commission and Argonne National Laboratory (page images at HathiTrust) Nuclear Superheat Meeting. No. 2 : April 7 and 8, 1960, Dunedin, Florida (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1960., 1960), by Florida) Nuclear Superheat Meeting (2nd : 1960 : Dunedin and U.S. Atomic Energy Commission. Chicago Operations Office (page images at HathiTrust) Nuclear Superheat Meeting. No. 4 : April 13 and 14, 1961, Idaho Falls, Idaho (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1961., 1961), by Idaho) Nuclear Superheat Meeting (4th : 1961 : Idaho Falls, Daniel E. Simpson, Andrew E. Mravca, and U.S. Atomic Energy Commission. Chicago Operations Office (page images at HathiTrust) Nuclear Superheat Meeting. No. 5 : September 13, 14, and 15, 1961, San Jose, California (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1961., 1961), by California) Nuclear Superheat Meeting (5th : 1961 : San Jose, Daniel E. Simpson, Andrew E. Mravca, and U.S. Atomic Energy Commission (page images at HathiTrust) Proceedings of the Nuclear Superheat Meeting. No. 7 : September 12, 13, and 14, 1962, Sioux Falls, South Dakota (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1962., 1962), by South Dakota) Nuclear Superheat Meeting (7th : 1962 : Sioux Falls, U.S. Atomic Energy Commission. Chicago Operations Office, and U.S. Atomic Energy Commission. Division of Technical Information (page images at HathiTrust) Small-sized nuclear power plant program (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service Extension, 1959., 1959), by U.S. Atomic Energy Commission (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) Boiling water reactor with internal superheater : Pathfinder Atomic Power Plant final feasibility report (Oak Ridge, Tennessee : U.S. Atomic Energy Commission, Technical Information Service, 1959., 1959), by Allis-Chalmers Manufacturing Company, Central Utilities Atomic Power Associates, Pathfinder Atomic Power Plant, Northern States Power Company (Wisconsin), and U.S. Atomic Energy Commission (page images at HathiTrust) 1000-MWE central station power plants investment cost study ([Washington, D.C.] : [For sale by the Supt. of Docs., U.S. Govt. Print Off.], 1972., 1972), by inc United Engineers & Constructors and U.S. Atomic Energy Commission. Division of Reactor Development and Technology (page images at HathiTrust) Design study of small boiling reactors for power and heat production (Oak Ridge, Tennessee : U.S. Atomic Energy Commission, 1954., 1957), by M. Treshow (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) Standard technical specifications for General Electric boiling water reactors. (Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Operating Reactors ;, 1978), by U.S. Nuclear Regulatory Commission. Division of Operating Reactors (page images at HathiTrust) Standard technical specifications for General Electric boiling water reactors (Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Operating Reactors ;, 1979), by Robert R. Bottimore and U.S. Nuclear Regulatory Commission. Division of Operating Reactors (page images at HathiTrust) Theoretical feedback analysis in boiling water reactors (Argonne National Laboratory, 1960), by Ziyaeddin A. Akcasu, Franco Velon©Ła, U.S. Atomic Energy Commission, University of Chicago, and Argonne National Laboratory (page images at HathiTrust) Power removal from a boiling reactor (Oak Ridge, Tennessee : Oak Ridge National Laboratory, 1952., 1952), by Paul Carl Zmola, E. N. Lawson, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust) Boiler reactor operation. Part III, Criticality requirements and plutonium production rates of bare, homogeneous reactors (Oak Ridge, Tennessee : Oak Ridge National Laboratory, 1953., 1953), by Paul R. Kasten, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory (page images at HathiTrust) Burnout limit curves for boiling water reactors (San Jose, California : General Electric Company, Atomic Power Equipment Department, 1962., 1962), by E. Janssen, S. Levy, U.S. Atomic Energy Commission, and General Electric Company. Atomic Power Equipment Department (page images at HathiTrust) Boiling light water reactor physics (San Jose, California : General Electric Company, Atomic Power Equipment Department, Vallecitos Atmoic Laboratory, 1962., 1962), by T. M. Snyder, Vallecitos Atomic Laboratory, U.S. Atomic Energy Commission, and General Electric Company. Atomic Power Equipment Department (page images at HathiTrust) An analysis of fluctuations in a boiling water reactor by methods of stochastic processes (San Jose, California : General Electric Company, Atomic Power Equipment Department, 1962., 1962), by P. R. Pluta, U.S. Atomic Energy Commission, and General Electric Company. Atomic Power Equipment Department (page images at HathiTrust) Phase velocities in boiling flow systems by total energy and by diffusion (San Jose, California : General Electric Company, Atomic Power Equipment Department, 1964., 1964), by Edward E. Polomik, U.S. Atomic Energy Commission, and General Electric Company. Atomic Power Equipment Department (page images at HathiTrust) Survey of high-temperature demineralization for dual-purpose BWR plants (Bethesda, Maryland : Allis-Chalmers Manufacturing Company, Atomic Energy Division, 1965., 1965), by Peter F. Santoro, Peter M. Lang, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory (page images at HathiTrust) Preliminary design requirements Argonne Boiling Reactor (ARBOR) facility (Argonne National Laboratory, 1957), by J. F. Matousek, C. F. Bullinger, S. A. Bernsen, and L. W. Fromm (page images at HathiTrust) Idaho Division summary report : October 1961 through September 1962 (Argonne National Laboratory, Idaho Division, 1962), by Meyer Novick and Argonne National Laboratory (page images at HathiTrust) Fabrication of UO2-stainless steel dispersion fuel for BORAX-V nuclear superheat (Argonne National Laboratory, Metallurgy Division, 1963), by W. C. Kramer, C. H. Bean, and Argonne National Laboratory (page images at HathiTrust) Idaho Division summary report : October 1960 through March 1961 (Argonne National Laboratory, Idaho Division, 1961), by Meyer Novick and Argonne National Laboratory (page images at HathiTrust) Reactor Engineering Division, Quarterly report Section II : April, May, June, 1956. (Argonne National Laboratory, Reactor Engineering Division, 1956), by Argonne National Laboratory (page images at HathiTrust) A performance analysis of the EBWR at various power levels (Argonne National Laboratory, Reactor Engineering Division, 1963), by Alfred A. Nentwich 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) 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) United States participation in the OEEC Halden reactor project, May 1959 to September 1960 (Argonne National Laboratory, 1960), by Leonard W. Fromm and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust) Idaho Division summary report : July, August, September, 1960 (Argonne National Laboratory, Idaho Division, 1960), by Meyer Novick and Argonne National Laboratory (page images at HathiTrust) 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) Hazard summary report on the Experimental Boiling Water Reactor (EBWR) (Argonne National Laboratory, 1958), by J. M. West and Argonne National Laboratory (page images at HathiTrust) 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) Manufacture of fuel plates for the experimental boiling water reactor (Argonne National Laboratory, 1957), by R. E. Macherey and Argonne National Laboratory (page images at HathiTrust) Design and hazards summary report Boiling Reactor Experiment V (BORAX V) (Argonne National Laboratory, 1961), by R. E. Rice and Argonne National Laboratory (page images at HathiTrust) Stationary Low Power Reactor No. 1 annual operating report (U.S. Atomic Energy Commission, Division of Technical Information, 1961), by U.S. Atomic Energy Commission and inc Combustion Engineering (page images at HathiTrust) Investigation on stability of a boiling heavy water reactor (U.S. Atomic Energy Commission, Division of Reactor Development, 1962), by Hiroshi Nishihara, Hideaki Nishihara, and U.S. Atomic Energy Commission. Division of Technical Information (page images at HathiTrust) Operational tests of EBWR vapor recovery system (Argonne National Laboratory, 1960), by R. J. Gariboldi, D. R. Jacobson, U.S. Atomic Energy Comission, and Argonne National Laboratory. Reactor Engineering Division (page images at HathiTrust) Preliminary design and hazards report boiling reactor experiment V (BORAX V). (Argonne National Laboratory, 1960), by R. E. Rice and Argonne National Laboratory (page images at HathiTrust) Zero-power experiments with boiling core B-1, BORAX-V (Argonne National Laboratory, Idaho Division, 1963), by Argonne National Laboratory (page images at HathiTrust) An evaluation of reactor concepts for use as separate steam superheaters (Argonne National Laboratory, Reactor Engineering Division, 1961), by D. H. Lennox and Argonne National Laboratory (page images at HathiTrust) Hazards evaluation report associated with the operation of EBWR at 100 MW (Argonne National Laboratory, 1959), by E. A. Wimunc, J. M. Harrer, and Argonne National Laboratory (page images at HathiTrust) Vallecitos Boiling Water Reactor stability test report (U.S. Atomic Energy Commission, Division of Technical Information, 1963), by General Electric Company. Atomic Power Equipment Department 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) Experiment data report for instrumented fuel assembly IFA-226 ([Washington, D. C.] : Dept. of Energy, Idaho Operations Office, 1978., 1978), by Judith A. Ramsthaler, Geraldine S. Reilly, Dennis E. Owen, U.S. Nuclear Regulatory Commission, Germeshausen & Grier Edgerton, and United States. Department of Energy. Idaho Operations Office (page images at HathiTrust) The effects of torus wall flexibility on forces in the Mark I boiling water reactor pressure suppression system : final report (Washington, D. C. : U.S. Nuclear Regulatory Commission, 1979., 1979), by Stephen C. H. Lu, E. W. McCauley, Garry S. Holman, Lawrence Livermore Laboratory, and U.S. Nuclear Regulatory Commission (page images at HathiTrust) Coupled fluid-structure method for pressure suppression analysis (Washington, D.C. : Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Reactor Safety Research, 1979., 1979), by William Herbert McMaster, N. A. Macken, B. Moran, E. Y. Gong, D. F. Qui©Þnones, G. L. Goudreau, D. M. Norris, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Lawrence Livermore Laboratory (page images at HathiTrust) Sloshing of water in torus pressure-suppression pool of boiling water reactors under earthquake ground motions (Washington, D.C. : Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Reactor Safety Research, 1979., 1979), by M. Aslam, D. T. Scalise, W. G. Godden, Lawrence Berkeley Laboratory, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust) Sloshing of water in annular pressure-suppression pool of boiling water reactors under earthquake ground motions (Washington, D.C. : Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1979., 1979), by M. Aslam, D. T. Scalise, W. G. Godden, Lawrence Berkeley Laboratory, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust) Final data report for the instrumented fuel assembly (IFA)-432 (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1982., 1982), by E. R. Bradley, D. D. Lanning, M. E. Cunningham, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust) Final surveillance of EBWR pressure vessel following the plutonium recycle program (Argonne, Ill. : Argonne National Laboratory, 1968., 1968), by N. Balai, M. R. Sims, C. R. Sutton, and Argonne National Laboratory (page images at HathiTrust) In-core activation traverses during the plutonium recycle experiment in the experimental boiling water reactor at power levels of 35 to 70 mw (Argonne, Illinois : Argonne National Laboratory, 1968., 1968), by R. E. Grajeck, K. E. Freese, and Argonne National Laboratory (page images at HathiTrust) STREAC : a boiling water reactor thermal and hydraulic code (Windsor, Connecticut : Combustion Engineering, Inc., Nuclear Division, 1961., 1961), by E. P. Hunger, F. Rodante, L. C. Noderer, and U.S. Atomic Energy Commission. Idaho Operations Office (page images at HathiTrust) Experiment data report for Test RIA 1-2 : (reactivity initiated accident test series) (The Commission ;, 1979), by Carolyn L. Zimmerman, Robert P. Evans, Christine E. White, Idaho National Engineering Laboratory, United States. Department of Energy. Idaho Operations Office, U.S. Nuclear Regulatory Commission, and EG & G Idaho (page images at HathiTrust) An analysis of proposed BWR inlet flow blockage experiments using MAYU-4b (The Commission :, 1982), by M. E. Nissley, Richard T. Lahey, Rodney R. Gay, Idaho National Engineering Laboratory, United States. Department of Energy. Idaho Operations Office, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
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