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Design Study: Sodium Modular Reactor

Description: This study was undertaken for the USAEC under Contract AT(04-3)-189, Project Agreement No. 6, to investigate desirable features of a sodium cooled, graphite moderated uranium fueled power reactor using the modular concept, and, based on this investigation, evaluate the economic potential of this reactor type.
Date: January 15, 1960
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation monthly activities report, December 1959

Description: This is the monthly report for the Hanford Laboratories Operation, January 1960. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: January 15, 1960
Partner: UNT Libraries Government Documents Department
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A LINEAR INDUCTION PUMP FOR LIQUID METALS

Description: A linear induction pump of a special design was used to circulate molten sodium through a mockup of an experimental "overflow" type of sodium-cooled reactor. The distinctive features of this pump are that no seals or moving parts are required: no piping is required to carry sodium to the pump or away from it because the pump is mounted directly on the reactor vessel, with the windings outside of the vessel and the magnetic flux return path inside the vessel. The pump develops 342 gpm at 6.2 psi… more
Date: January 15, 1960
Creator: Baker, R.S.
Partner: UNT Libraries Government Documents Department
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NUCLEAR CHARACTERISTICS OF BeO-MODERATED CORES VS. GRAPHITE-MODERATED CORES

Description: Multigroup calculations were performed to compare BeO-moderated cores with graphite-moderated cores, using various void fractions and core diameters. The core leakages and conversion ratios which were calculated are presented in a series of curves. (auth)
Date: January 15, 1960
Creator: Carlsmith, R.S.
Partner: UNT Libraries Government Documents Department
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Progress Report for Period Covering December 17, 1969 - January 15, 1960

Description: As reported in the previous Progress Report (December 16, 1959) a stock solution of Th 230 was prepared from pitchblende. Pulse height analysis of this solution indicated the presence of only Th 230 (93%), Th 227 (5%), Th 232 (1%), and Th 228 (1%). This solution was used to make up synthetic thorium solution of various concentration. These synthetic solutions were analyzed to establish a chemical yield for the procedure. Neither the precision nor the chemical yield of the procedure were conside… more
Date: January 15, 1960
Creator: Petrow, Henry G.
Partner: UNT Libraries Government Documents Department
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Radioactive Drug Research, Final Summary Report, July 1949 to October 1959

Description: Applications of radioisotopes in the preparation of labeled drugs are reviewed. Among the applications described are the preparation of carbon-14- labeled cardiac glycosides, and the biosyinthesis of carbon-14-labeled digitoxin, morphine, colchicine, atropine, podophyllotoxin, and nicotine. The fate and metabolism of many of these drugs were traced. Radiochemical procedures were developed for the synthesis of pure compounds of pharmacological interest labeled with carbon-14, sulfur-35, and trit… more
Date: January 15, 1960
Creator: Geiling, E. M. K. (Eugene Maximilian Karl), 1891-1971 & Roth, Lloyd J. (Lloyd Joseph), 1911-
Partner: UNT Libraries Government Documents Department
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The Snap-Ii Power Conversion System. Dynamic Analysis. Topical Report No. 3

Description: SNAP II is the designation for a nuclear auxiliary power unit, designed primarily for utilization in the WS117L satellite vehicle. The SNAP II system consists of a reactor heat source, a mercury Rankin engin, and an alternator. Dynamic analysis of the power conversion system was conducted utilizing a comprehensive analog computer simulation. Feasibility of a parasitic load control for numerous system disturbances was demonstrated. (auth)
Date: January 15, 1960
Creator: Deibel, D. L.; Mrava, G. L. & Seldner, K.
Partner: UNT Libraries Government Documents Department
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The SNAP II Power Conversion System. Topical Report No. 3. Dynamic Analysis

Description: SNAP II is the designation for a nuclear auxiliary power unit, designed primarily for utilization in the WS117L satellite vehicle. The SNAP II system consists of a reactor heat source, a mercury Rankine engine, and an alternator. Dynamic analysis of the power conversion system was conducted utilizing a comprehensive analog computer simulation. Feasibility of a parasitic load control for numerous system disturbances was demonstrated. This analysis was performed under a subcontract to to Atomics … more
Date: January 15, 1960
Creator: Deibel, David L.; Mrava, Gene L. & Seldner, Kurt
Partner: UNT Libraries Government Documents Department
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SNAP II POWER CONVERSION SYSTEM TOPICAL REPORT NO. 11, ORBITAL FORCE FIELD BOILING AND CONDENSING EXPERIMENT

Description: The characteristics of Rankine space power plants in the zero gravity aspect of the environment of space were lnvestigated. The expected effects of Rankine space power plants are described. Discussions of experimental techniques for studying these phenomena show that this information can be obtained rapidly and economically. Recommendations for a program to supplement SNAP II and slmllar Ranklne space power development efforts in this vital area are made, and consist of: the development and tes… more
Date: January 15, 1960
Creator: Grevstad, P.E.
Partner: UNT Libraries Government Documents Department
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Studies of Reactor Containment : Monthly Technical Progress Report No. 32

Description: The report covers work performed during the period December 1, 1959 through December 31, 1959. The general objectives of the program of "Studies of Reactor Containment" are to accomplish theoretical and experimental investigations of the loads to which external containment structures for nuclear reactors are subjected in the vent of a violent incident at the reactor core, the evaluation of methods of reducing that loading, and the study of the response of and design criteria for external contai… more
Date: January 15, 1960
Creator: Zaker, T. A. (Thomas Allen)
Partner: UNT Libraries Government Documents Department
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TRANSIENT BUBBLE GROWTH IN A HOMOGENEOUS REACTOR

Description: A mechanism for shutting off a power excursion in a homogeneotns reactor by the rapid formation of bubbles was investigated. Equations are derived which give upper and lower bounds for the radius of a bubble, as a function of time, under conditions present in a reactor. Deduction of the bubble nuclei growth rate from observations of void volume and pressure can be made. (auth)
Date: January 15, 1960
Creator: Flatt, H. P.
Partner: UNT Libraries Government Documents Department
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Ultrasonic Resin Level Detector

Description: This report describes the development of an ultrasonic instrument for resin level measurements in an ion exchange column.
Date: January 15, 1960
Creator: Hunter, D. O. & Pleasance, C. L.
Partner: UNT Libraries Government Documents Department
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Upper Atmosphere Monitoring Program : Progress Report No. 8 for May 1, 1959 through July 31, 1959

Description: The overall scope of the program encompasses both research into the physical parameters involved in the collection of airborne radioactive particles and the development, fabrication and calibration of balloon-borne sampling equipment to enable the precise determination of stratospheric particle concentration and particle size distribution.
Date: January 15, 1960
Creator: Baumstark, J.; Jones, S.; Stern, S.; Torgeson, L. & Zeller, W.
Partner: UNT Libraries Government Documents Department
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Critical Mass Studies of Plutonium Solutions

Description: Chain reacting conditions for plutonium nitrate in water solution have been examined experimentally for a variety of sizes of spheres and cylinders.
Date: February 15, 1960
Creator: Kruesi, F. E.; Erkman, J. O. & Lanning, D. D.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation monthly activities report, January 1960

Description: R and D is reported in the following: Reactor and Fuels (PRTR, Pu fabrication pilot plant, KER, NPR, materials); Chemical R and D (Pm recovery, fission products, Purex column, non-production fuels reprocessing, Salt Cycle process); Physics and Instrument R and D (PCTR, NPR, critical experiments, PRTR); and Biology (monitoring, irradiation experiments).
Date: February 15, 1960
Partner: UNT Libraries Government Documents Department
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The Irradiated Rupture Prototype (IRP) Design

Description: One of the problems involved in the design of NPR is the method to be used for decontamination, Considerable effort has been made in both laboratories and pilot plants in developing and evaluating decontamination processes under ideal conditions. Promising processes must be tested under prototypical conditions of velocity, water quality, manner of make-up, type and degree of contamination, addition of decontaminating solutions, and so on.
Date: February 15, 1960
Creator: Neibaur, G. E. & Stice, N. D.
Partner: UNT Libraries Government Documents Department
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Maximum Volume-to-Stress Ratio for a Two-Radii-Contour Diaphragm Pump

Description: Analytical methods were employed to determine the maximum volume-to- stress ratio for a two-radii-contour diaphragm pump. A proposed failure criterion considers the effect of biaxial stresses on fatigue failure through. the use of the Mises-Hencky criterion for fatigue failure. By use of the proposed criterion, it was determined that an optimunn ratio of the two radii does exist, its value being dependent on the ratio of diphragm thickness to diaphragm deflection. Values for the optimum ratio o… more
Date: February 15, 1960
Creator: Cheverton, R. D.
Partner: UNT Libraries Government Documents Department
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Progress letter No. 11 for January 1, 1960 through January 31, 1960

Description: A stainless steel autoclave for superheated water corrosion test was installed and "conditioned". Tests were begun to investigate the feasibility of densifying slip cast stainless steel by means of liquid phase sintering. Attempts to prepare tubular fuel elements by vacuum forming were resumed. Although thick-walled vacuum formed casting have been sintered on the aluminum mandrels without cracking, this has not yet been accomplished with the think sections of interest.
Date: February 15, 1960
Creator: Baron, Edeard H.
Partner: UNT Libraries Government Documents Department
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Progress Report for Period Covering January 15, 1960 - February 15, 1960

Description: Thorium Procedure: As was mentioned in the last report, ammonium nitrate was substituted for ferric nitrate as a salting agent. Also, the acidity of the nitrate solution was reduced from 3.0 molar to 0.5 molar. the revised thorium procedure is described in the report. Radium Procedure: Work has ben initiated on the procedure of Petrow, Nietzel and DeSesa (Winchester Procedure) to determine if the procedure is suitable for very low level concentrations of radium.
Date: February 15, 1960
Creator: Petrow, Henry G.
Partner: UNT Libraries Government Documents Department
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Reactor hazards review zirconium retubing of Hanford reactors

Description: This report examines the pertinent features in the hazards analyses of the Hanford Reactors which may be affected by the substitution of zirconium tubes for the present aluminum process tubes. Resized I & E slugs, designed to preserve present pressure drops across the active zones and to minimize corrosion, are used as examples to compare the characteristics of the zirconium tubes reactor with the present.
Date: February 15, 1960
Creator: Nilson, R.
Partner: UNT Libraries Government Documents Department
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An Advanced Sodium-Graphite Reactor Nuclear Power Plant

Description: Abstract: This report describes an advanced sodium-cooled, graphite-moderated nuclear power plant which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency.
Date: March 15, 1960
Creator: Churchill, J. R. & Renard, J.
Partner: UNT Libraries Government Documents Department
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AN ADVANCED SODIUM-GRAPHITE REACTOR NUCLEAR POWER PLANT

Description: An advanced sodium-cooled, graphite-moderated nuclear power plant is described which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency. Steam is generated at 2400 psig, superheated to 1050 deg F and, after partial expansion in the turbine, reheated to 1000 deg F. Net thermal efficiency of the plant is 42.3%. In a plant sized to produce a net electrical output of 256 Mw, the estimated cost is 8232/kw. Estimated cost of power generation is 6.7 mil… more
Date: March 15, 1960
Creator: Churchill, J. R. & Renard, J.
Partner: UNT Libraries Government Documents Department
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