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Technical Information, Preliminary Hazards Summary Report, Volume 2, Part B: License Application

Description: Report describing the reactor design, nuclear plant design, existing power generation facilities, and plant organization of the Carolinas–Virginia Tube Reactor. Mechanical design, the primary plant system, primary plan auxiliary systems, reactor and primary plant control and instrumentation, and containment of vapors are discussed.
Date: July 15, 1959
Creator: Carolinas Virginia Nuclear Power Associates, Inc.
Partner: UNT Libraries Government Documents Department
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Allis-Chalmers Critical Facility: Final Safeguards Report

Description: Report discussing the final safeguards integrated into the design of the Pathfinder Atomic Power Plant for the Northern States Power Company. The plant is designed by the Allis-Chalmers Manufacturing Company in Greendale, Wisconsin. Description of the facility, operating procedures, experiments, accident analysis, safety features of the reactor, and make up of the surrounding area are included.
Date: May 1, 1959
Creator: Allis-Chalmers Manufacturing Company
Partner: UNT Libraries Government Documents Department
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Upper Atmosphere Monitoring Program. Progress Report No. 6 Covering period November 1, 1958 to January 31, 1959. Report No. 1903

Description: Programs of research into the physical parameters involved in the collection of airborne radioactive particles and the development, fabrication, and calibration of balloon-borne particle sampling equipment to implement the precise determination of stratospheric particle concentration and particle size distribution are reported. A two-stage rectangular jet impactor which collects airborne particles by impingement on a flat plate and is designed to obtain data on size distribution was fabricated.… more
Date: May 1, 1959
Creator: Baumstark, J;; Torgeson, L;; Stern, S;; Schekman, A; & Zeller, W
Partner: UNT Libraries Government Documents Department
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Sodium-Air Accident Study for a Sodium Cooled Reactor. Technical Memorandum No. 20

Description: The design requirements of a containment building for a sodium-cooled reactor have been investigated from the point of view of a hypothetical sodium - air reaction. In particular, this study was directed toward the containment building of the Enrico Fermi Atomic Power Plant. The hypothetical accident assumes a major leak in the sodium system with a concurrent or earlier failure of the ventilation and cooling systems which allows air to enter the areas around the sodium system which are normally… more
Date: April 6, 1959
Creator: Garelis, Edward
Partner: UNT Libraries Government Documents Department
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Reactor Automatic Control and Load Swing Test. Test Results DL-S-144 (T-554924). Section I. Second Performance

Description: The purpose of this test was to determine the controlling ability of the Reactor Power and Temperature Control System and to determine the operational characteristics of the station during load swings after change of operating conditions from 523 F, 2000 psi, to 500 F, 1800 psi. The Reactor Power and Temperature Control System satisfactorily controlled rod movements to maintain all primary plant parameters within their individual limits during steady state operation and during ramp function loa… more
Date: March 25, 1959
Creator: Mafrica, Roces
Partner: UNT Libraries Government Documents Department
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Air Diffusion in the Air Operating Water Flask. Section I. Test Results DL-S-205 (T-641110)

Description: The purpose of the test was to determine the effect of continuous air pressurization of the Valve Operating System water flask on the the oxygen concentration of the water in the flask. Oxygen concentration in the Valve Operating System water flask increased during the testing period of seventeen days. It cannot be determined from the data obtained if equilibrium oxygen concentration was reached. The distribution of oxygen in the flask at the end of 17 days varied from approximately 12 ppm in t… more
Date: March 24, 1959
Creator: Beckwith, Robert A.
Partner: UNT Libraries Government Documents Department
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Control Rod Positions for Criticality. Section II. Fifth Performance.1692.2 EFPH. Test Results DL-S-149 (T-550130)

Description: The purpose of the test was to determine critical bank heights and bank worths for various rod configurations at normal plant operating temperature and pressure after 1692.8 EFPH's of Reactor operation. The critical bank heights and bank worths were determined for six different control rod configurations at a coolant temperature and pressure of 520 F and 1780 psig and are charted in the report.
Date: March 24, 1959
Creator: McTish, James M.
Partner: UNT Libraries Government Documents Department
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Control Rod Positions for Criticality. Section I. Fourth Performance. Test Results DL-S-149 (T-550130)

Description: The purpose of the test was to determine critical bank heights and bank worths for various rod configurations at ambient temperature. The critical bank heights and bank worths at a coolant temperature and pressure of 130F and 400 psig were determined and are charted in the report. The test was performed after 556.6 EFPE of operation of the station.
Date: March 24, 1959
Creator: Baird, John B.
Partner: UNT Libraries Government Documents Department
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Sample Connector and Cable Radiation Measurements. Test Results DL-S-260-S (RNI-9). Section I

Description: The purpose of the test was to determine total radioactivity due to activation and possible contamination of six special connectors and a length of cable suspended in Nuclear Instrument Channel D source range detector well during the performance of the second Reactivity Lifetime Test. This data was to be used to estimate the effective gamma and beta-gamma activity half lives of the sample. The effective gamma and beta gamma half lives of the samples cannot be determined from the information ava… more
Date: April 20, 1959
Creator: Price, F. C.
Partner: UNT Libraries Government Documents Department
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Fuel Handling, Service and Waste Disposal Buildings Drain Test. Section I. Test Results DL-S-230 (T-641115)

Description: The purpose of the test was to prove the integrity of the non-active drains, the special drains, the sanitary drains, the chemical waster drains and the storm water drains by means of a water flow test and visual inspection. The two roof boxes and the one floor drain of 1B Auxiliary Equipment Room did not drain properly. The lab sink in the west end of the Radiochemistry Lab drained to the Special Monitored West Transfer Tank instead of the Monitored Waster Transfer Tank. All other drains funct… more
Date: March 31, 1959
Creator: Barclay, Richard E.
Partner: UNT Libraries Government Documents Department
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Control Rod Positions for Criticality. Section II. Fourth Performance. Test Results DL-S-149 (T-550130)

Description: The purpose of the test was to determine critical bank heights and bank worths for various rod configurations at normal plant operating temperature and pressure. The critical bank heights and bank worths were determined for various rod configurations after 560 EFPH's of reactor operations are charted in the report.
Date: March 31, 1959
Creator: Baird, John B.
Partner: UNT Libraries Government Documents Department
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The Circular Polarization of Gamma Radiation Following Allowed Beta Transitions

Description: The degree of circular polarization of gamma rays following allowed beta transitions was investigated as a function of the angle THETA /sub beta gamma / between beta-particle momentum and gamma direction and as a function of the energy of the beta particle. The anisotropy of the beta-gamma circular polarization correlation observed for pure Gamow-Teller transitions ( DELTA 1 = 1) is used to determine the validity of C/sub A/' = C/sub A/. The experimental results for Co/sup 60/ and Na/sup 22/ ar… more
Date: January 1959
Creator: Steffen, R. M. (Rolf M.), 1922-
Partner: UNT Libraries Government Documents Department
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Bibliography on Uranium Dioxide

Description: A bibliography of 284 references to AEC reports US patents and the periodical literature of the world.
Date: March 1959
Creator: Hausner, Henry H. (Henry Herman), 1901-1995
Partner: UNT Libraries Government Documents Department
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Supplement No. 2. Supplemental Data for Nuclear-Conventional Power Plant Cost Study. Conventional Coal Fired Power Plants : 25,000 KW to 325,000 KW for Evaluation and Planning Branch, Division of Reactor Development, Atomic Energy Commission

Description: In order to establish a basis for comparing the estimated cost of nuclear power plant designs, a set of general and detailed design considerations for conventional coal-fired power plants was established. Five preliminary designs of conventional coal-fired power plants ranging in size from 25to 325 mw were selected, and cost estimates were prepared. Supplement No. 2 furnishes the following requested information.: (1) Projected investments costs, 1959-1975 for each of the five unites sizes; (2) … more
Date: September 1, 1959
Creator: Chittenden, W. A.
Partner: UNT Libraries Government Documents Department
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Supplement No. 1. Projections of Costs, 1959-1975 for Nuclear-Conventional Power Plant Cost Study. Conventional Coal Fired Power Plants : 25,000 KW to 325,000 KW for Argonne National Laboratory, Lemont, Illinois

Description: In order to establish a basis for comparing the estimated cost of nuclear power plant designs, a set of general and detailed design considerations for conventional coal-fired power plants was established. Five preliminary designs of conventional coal-fired power plants ranging in size from 25to 325 mw were selected, and cost estimates were prepared. Supplement 1 shows a year by year projection of costs for the period 1959-1975.
Date: July 2, 1959
Creator: Chittenden, W. A.
Partner: UNT Libraries Government Documents Department
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Nuclear-Conventional Power Plant Cost Study. Conventional Coal Fired Power Plants : 25,000 KW to 325,000 KW for Argonne National Laboratory, Lemont, Illinois

Description: In order to establish a basis for comparing the estimated cost of nuclear power plant designs, a set of general and detailed design considerations for conventional coal-fired power plants was established. Five preliminary designs of conventional coal-fired power plants ranging in size from 25to 325 mw were selected, and cost estimates were prepared. ( A.C.)
Date: March 2, 1959
Creator: Chittenden, W. A.
Partner: UNT Libraries Government Documents Department
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Organic Coolant Reclamation. First Quarterly Progress Report for December 15, 1958 - March 15, 1959

Description: In research on developing a suitable method for organic coolant reclamation, several lines of attack are being followed simultaneously. Model compounds have been utilized in initial experiments. For the vapor phase hydrogenation-cracking study, apparatus has been constructed and several catalysts screened. A nickel on kieselguhr catalyst has been shown to be active in converting biphenyl to a mixture of benzene and toluene. Liquid phase hydrogenation techniques are under study for partial reduc… more
Date: April 15, 1959
Creator: Wineman, Robert J.; Gudzinowicz, Benjamin J.; Lopiekes, D. V. & Scola, D. A.
Partner: UNT Libraries Government Documents Department
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14-Year 113Cd

Description: The half lives of Cd/sup 113m/ and Cd/sup 115m/ have been redetermined to be 14 sintering time 2 years and 44.2 sintering time 0.5 days, respectively. The ratio of Cd/sup 113m/Cd/sup 115m/ yields from thermal-neutron fission of U/sup 235/ is 0.27 sintering time 0.03, and the ratio of (n, ) formation cross sections is 0.31 sintering time 0.03. Combination of these ratios with literature values for the Cd/sup 115m/ fission yield and (n, ) formation cross section gives (1.9 sintering time 0.2) x 1… more
Date: October 31, 1959
Creator: Wahl, Arthur C.
Partner: UNT Libraries Government Documents Department
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The Separation of the CuSO4-CoSO4-H2O System in a Horizontal Thermal Diffusion Column

Description: A horizontal thermal diffusion column was constructed and operated in the separation of CuSO4-CoSO4-H2O, each salt being 0.5 molal. The equilibrium constant for mass transfer as 0.82 for separation of CuSO4 from water and 0.86 for CoSO4. It was concluded that this method is suitable for separating the salt mixtures, the height of the transfer unit is proportional to the flow rate for total reflux operation, and the separation of each salt from water is independent of the other salt. (T.R.H.).
Date: June 1959
Creator: Fisher, Gerald Thomas & Prados, J. W.
Partner: UNT Libraries Government Documents Department
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Suggestion for an Investigation Leading to the Development of a "Steam-Quality" Gage

Description: An instrument was developed for measuring the water droplet content of steam through its relationship to the acoustic properties of the steam . The experimental work associated with this particular phase was directed toward the more immediately pressing problems of reactor safety, and measurements were made on the propagation of large amplitude waves through boiling water.
Date: 1959
Creator: Karplus, H. B.
Partner: UNT Libraries Government Documents Department
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Iodine Monitoring at the National Reactor Testing Station

Description: Operations at the National Reactor Testing Station generally involve new types of fuel elements or reactors or the chemical processing of spent fuel elements. Because the isotopes of iodine are produced in high yield during fission and their short half lives permit equilibrium concentrations to be built up rapidly considerable inventories of these isotopes will be present after a reactor has operated for a relatively short length of time. The gaseous nature of the element allows its escape afte… more
Date: March 23, 1959
Creator: Sill, Claude W. & Flygare, J. Kenneth, Jr.
Partner: UNT Libraries Government Documents Department
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