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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 when pumping sodium at 600 deg F with an efficiency of 4.7%. (auth)
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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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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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 testing of a small system that adequately simulates a complete Ranklne system, first in zero grayity and finally, in the complete orbltal environment; followed by, the development and similar testing of a complete Rankine system using SNAP ll hardware. (auth)
Date: January 15, 1960
Creator: Grevstad, P.E.
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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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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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 of the two radii (where the ratio of radii is defined as the radius of the central pcrtion of the diaphragm contour divided by the radius of the outer pontion of the diaphragm) range from 1.94 to 7.33 as the ratio of diaphragm thickness to diaphragm deflection varies from 0.5 to 0.05, respectively. (auth)
Date: February 15, 1960
Creator: Cheverton, R. D.
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 mills/kwh. In a similar plant with a net electrical output of 530 Mw, the estimated power generating cost is 5.4 mills/ kwh. Most of the components of the plant are within the capability of current technology. The major exception is the fuel material, uranium carbide. Preliminary results of the development work now in progress indicate that uranium carbide would be an excellent fuel for high-temperature reactors, but temperature and burnup limitation have yet to be firmly established. Additional development work is also required on the steam generators. These are the single-barrier type similar to those which will be used in the Enrico Fernri Fast Breeder Reactor plant but produce steam at higher pressure and temperature. Questions also remain regarding the use of nitrogen as a cover gas over sodium at 1200 deg F and compatibility of the materials used in the primary neutron shield. All of these questions are currently under investigation. (auth)
Date: March 15, 1960
Creator: Churchill, J. R. & Renard, J.
Partner: UNT Libraries Government Documents Department
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Graphite burnout, interim report on IP-25-A (PT-105-532-E)

Description: Graphite reacts with such gases as CO{sub 2}, O{sub 2}, or water vapor to form gaseous oxides of carbon. In the case of CO{sub 2}-graphite interaction, the reaction rate is not significant until about 550 C. Water oxidizes graphite, very roughly, three times faster than CO{sub 2}. Air will oxidize graphite appreciably at temperatures below 500 C. Graphite removal from Hanford reactors is very important, since graphite is used both as a structural support and a moderator for neutrons. Griggs has shown that small graphite samples oxidized to 10 per cent weight loss had only about one-half their original compression strength. Hence, the longevity of the reactors depends to a great extent on maintaining a low graphite oxidation rate. A means of monitoring the extent of graphite loss, i. e., the burnout rate, is necessary to establish future reactor operational standards. Presently, weighed samples of reactor grade graphite are placed along the length of an empty process channel in each reactor. Thus, a sample is exposed to the reactor`s ambient conditions of power level, moderator temperature, and gas composition. This program was initiated in the vicinity of June, 1953 by Woodley. This report presents data on graphite burnout obtained from in-reactor experiments authorized under IP-25-A (PT-105-532-E) from August, 1957 to January, 1960. Burnout rates are obtained by a direct measurement of the weight loss of control graphite samples exposed to the reactor atmosphere.
Date: March 15, 1960
Creator: Ryan, B. A. & de Halas, D. R.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation monthly activities report, February 1960

Description: This is the monthly report for the Hanford Laboratories Operation, February, 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: March 15, 1960
Partner: UNT Libraries Government Documents Department
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High Flux Isotope Reactor: a General Description

Description: Current status of the High Flux Isotope Reactor which is being planned for construction at Oak Ridge.
Date: March 15, 1960
Creator: Cole, T. E.
Partner: UNT Libraries Government Documents Department
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An IBM-704 Code for a Harmonics Method Applied to Two-Region Spherical Reactors

Description: An IBM-704 computer code for the harmonics method of criticality calculation for two-region spherical reactors is described. In the harmonics method, the criticality condition corresponds to the vanishing of a certain infiniteorder determinant; in practice, this condition is replaced by equating a finite-order approximating determinant to zero. By hand, the calculations can be performed conveniently only for second-order approximating determinants. The approximating determinant with the described code is customarily of the seventh order. Losses of significant figures prevented the use of larger determinants. The machine running time per case is generally about 30 sec. (auth)
Date: March 15, 1960
Creator: Chalkley, R.; Nestor, C. W. Jr. & Tobias, M. L.
Partner: UNT Libraries Government Documents Department
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Interim Report on Safety Procedures for the Task 2 Thermoelectric Generator

Description: Operational hazards associated with the use of a radioisotope-fueled auxiliary power unit for a satellite mission are evaluated. The entire fabrication-to-flight and/or retrieval and disposal sequence is examined and safe handling procedures suggested. The design and operation of the Task 2 thermoelectric generator is discussed. (C.J.G.)
Date: March 15, 1960
Creator: Klein, L. T.
Partner: UNT Libraries Government Documents Department
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PATHFINDER ATOMIC POWER PLANT TECHNICAL PROGRESS REPORT FOR OCTOBER 1959- DECEMBER 1959

Description: >Technical progress on the research and development program being performed in connection with the design of the Sioux Falls Power Reactor is reported. Areas covered in detail include fuel element research and development, reactor mechanical studies, nuclear analysis, chemistry, instrumentation and control, plant safety analysis, feasibility studies, and steam plant and reactor auxiliary systems design. (For preceding period see ACNP-5924.) (W.D.M.)
Date: March 15, 1960
Partner: UNT Libraries Government Documents Department
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PURIFICATION OF Pm$sup 147$ FROM FISSION-PRODUCED RARE EARTHS

Description: Promethium is purified from inactive and radioactive long-lived fission- produced rare earths by the use of Dowex 50 or Nalcite HCR cation exchangers and organic eluants. Americium and promethium, having hydrated ionic radii of the same size, are contained in the same fraction of the eluate. Promethium is purified from americium by adsorbing both elements on Dowex 1 (thiocyanate form) and eluting promethium from the resin with ammonium thiocyanate solution. Equllibrium studies were made in order to determine distribution coefficients of the long-lived radioactive rare earths. Elution curves based on analyses of solutions removed from anion and cation exchangers verify the relative values of the distribution coefficients. From Dowex 1 resin, rare earths 58 through 63 elute with ammonium thiocyanate in the order of increasing atomic number. Conditions are established for the expansion of the present 50- to 100-curie- level processing to levels of 1000 to 5000 curies. (auth)
Date: March 15, 1960
Creator: Pressly, R.S.
Partner: UNT Libraries Government Documents Department
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