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The SNAP II Power Conversion System. Topical Report No. 4. Turbine Design and Testing
SNAP II is the designation for a 3 KW nuclear auxiliary power unit to be used in a satellite vehicle. The SNAP II system consists of a reactor heat source, a mercury Rankine engine and an alternator. A two stage, full admission, axial flow turbine was chose for the APU application. Design details and test results are presented in this report. This work was performed under a subcontract to to Atomics International as part of the Atomic Energy Commission Contract No. AT(11-1)-GEN-8.
Date:
January 18, 1960
Creator:
Poulos, Earnest N. & Forman, Edward R.
System:
The UNT Digital Library
Core I Control Rod Drive Mechanisms Periodic Tests. Section I. Ninth Performance. Test Results DL-S-148-I, T-550011
The purpose of the test was to determine the operating conditions of the rod drive mechanisms so that operating personnel may be informed concerning malfunctioning mechanisms. The results the this test favorably agree with previous results. The operating characteristics of the rod drive mechanisms checked in this test have not changed appreciably.
Date:
November 18, 1959
Creator:
Pazuchanics, Nicholas
System:
The UNT Digital Library
Control Air Conditions at the Reactor Chamber. Section I. Test Results DL-S-269
The purpose of the test was to determine the ability of the Control Air System to provide the necessary quantity and quality of clean, dry air to keep the rod drive mechanism stator and position indicator housings at about 3 PSIG in order to avoid low stator resistances resulting from condensation during plant cooldown. The Control Air System is capable of providing the quality of air specified in AEC letter SBO:JWF:100 dated November 17, 1958 of less than 44 grains of moisture per lb. of air in the control air line nearest the reactor chamber.
Date:
November 18, 1959
Creator:
Eckenrode, Gerald E.
System:
The UNT Digital Library
Station Radiation Level Survey. Section II. Fifth Performance. Core I, Seed 1. Test Results DL-S-157
The purpose of the test was to determine the level of the radiation field in the Turbine Plant during a significant power run. The initial power level survey had an average radiation level of 0.02 mr/hr. this survey showed and average radiation level of 0.03, which was considered background level. this radiation level was far below the maximum allowable level of 2 mr/hyr. No Neutrons were detected.
Date:
November 18, 1959
Creator:
McTish, James M.
System:
The UNT Digital Library
Measurements of Coefficients of Reactivity. Section I. Seventh Performance. 3032-EFPH. Core I, Seed 1. Test Results DL-S-151 (T-550132)
The purpose of the test was to determine the temperature and pressure coefficients of reactivity at zero power. Data was obtained during this test which indicates a new temperature coefficient and a pressure coefficient corrected to station operating conditions of 500 F and 1785 PSIG.
Date:
November 18, 1959
Creator:
unknown
System:
The UNT Digital Library
Liquid Metal Level Instrument
Theory of operation and test results are given for a resistance type of liquid metal level instrument. The voltage across a steel rod in the tank is amplified by a magnetic amplifier and indicated by a milliammeter. Temperature compensation is provided for tank temperatures up to 1000 F.
Date:
March 18, 1952
Creator:
Robinson, H.; Dows, L. H. & Droms, C. R.
System:
The UNT Digital Library
Effect of Core Corrosion Sample Assembly on HRT Critical Concentration
An estimate has been made of the critical fuel concentration in the HRT, taking into account the effect of the core corrosion sample assembly. The estimate is based on a number of previous calculations of critical concentration in an un-poisoned reactor and one calculation of critical concentration as a function of poison level. The makeup of the first core corrosion sample assembly was used in calculating equivalent neutron poisoning effects. Figure 1 shows the estimated critical concentration as a function of temperature with the corrosion sample assembly in place. At 280°C, the assembly raises the critical concentration by 0.6 g U-235/kg D2O. This effect is equivalent to a uniformly distributed poison equal to 4.1% of the fission cross section. The equivalent poison is greater at lower temperatures, where the uranium concentration is lower.
Date:
July 18, 1957
Creator:
Haubenreich, Paul N.
System:
The UNT Digital Library
Trip to Selas Corporation of America
On May 23, 1957, a visit was made by the writer to the Selas Corporation of American in Dresher, Pennsylvania. The purpose of the visit was to discuss further investigations into methods of tubesheet brazing by direct heating. Original work along these lines has been carried out at ORNL and is covered by a memo (CF-57-4-57) to W.D. Manly, dated April 16, 1957, and entitled : Investigation of Tubesheet Brazing by a Method of Direct Heating.
Date:
June 18, 1957
Creator:
Franco-Ferreira, E. A.
System:
The UNT Digital Library
Liquid-Liquid Extraction of Uranium and Plutonium from Hydrochloric Acid Solution with TRI (Iso-Octyl) Amine. Separation of Uranium and Plutonium from Thorium and Fission Products
A new and rapid method for the liquid-liquid extraction of uranium and plutonium from hydrochloric acid solution is based on the use of tri(iso-octyl)amine dissolved in xylene or methylisobutylketone. Uranium and/or plutonium are separated from thorium, alkalis, alkaline earths, rare earths, zirconium, niobium, ruthenium and other elements which do not form anionic species under the conditions described. The technique may be used for either tracer or macro quantities of uranium. Several practical applications of the method for the separations chemist are proposed.
Date:
June 18, 1957
Creator:
Moore, Fletcher L.
System:
The UNT Digital Library
TBP Stripping in Bubble-Cap Column and Concomitant Product Evaporation
A study was conducted to demonstrate the stripping and evaporation steps in a Purex-type uranium recovery process and to ascertain the operating behavior of the equipment under a range of conditions. The factors considered were control, effectiveness, and reliability of equipment and optimum feed point. Experimental procedures are described, and recommendations for equipment modifications are included. (J.R.D.)
Date:
March 18, 1957
Creator:
Long, J. T.
System:
The UNT Digital Library
Annual Report of the Boy Scouts of America: 1954
Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1954, activities, organizational leadership, programming, membership, training, and other information about scouting programs.
Date:
March 18, 1955
Creator:
Boy Scouts of America
System:
The Portal to Texas History
Experimental Investigations of the Removal of Sodium Oxide From Liquid Sodium
Experimental investigations were conducted to obtain additional information on the growth and characteristics of sodium oxide deposits in liquid sodium which could lead to system plugging. These investigations included the removal of sodium oxide from molten sodium by the cold trap method.
Date:
January 18, 1960
Creator:
Billuris, G.
System:
The UNT Digital Library
NPR; Tube to Nozzle Connection and Zircaloy-2 to Stainless Steel Tube Connection
Zircaloy-2 tubing was successfully joined to austenetic and ferritic stainless steel tubing by fusion bonding. Tungsten inert gas welding was employed to join a flange to a pressure tube. This work was performed to help determine the design of pressure tubes of a pressure tube reactor.
Date:
November 18, 1958
Creator:
Smith, W. R. & Klepfer, H. H.
System:
The UNT Digital Library
Handling Techniques for Rubidium
Experience in handling and purifying rubidium metal, prior to high-temperature corrosion testing, has been obtained. Some of the physical and chemical properties of this metal are listed. Distillation and filtration experiences are described, and the analysis of samples following such purification procedures are given. Stripping procedures following corrosion testing are discussed briefly. Results of preliminary corrosion experiments indicate that Inconel in a satisfactory container material for boiling rubidium at temperatures up to 1520°F.
Date:
December 18, 1955
Creator:
McCoy, H.E., Jr. & Hoffman, E. E.
System:
The UNT Digital Library
Stable Isotope Research and Production Division Semiannual Progress Report
The Spectroscopy Research Laboratory is concerned with research and development in the fields of nuclear magnetic resonance, microwaves, infrared and optical spectroscopy, spectrochemistry, and x rays. Research is directed toward fruitful methods of isotope analysis; new element and compound analytical methods having application to immediate Laboratory or long-range commission needs; and fundamental research on isotopes, elements, and compounds. The work is reported on a project basis to give a more complete picture of the purpose, activity, and status of each program. More detailed information on reported or inactive projects may be obtained from the previous semiannual report.
Date:
February 18, 1955
Creator:
Keim, C. P.
System:
The UNT Digital Library
Electronuclear Research Division Semiannual Progress Report
Nuclear physics research with 22-Mev protons in the 86-in. cyclotron included angular-distribution measurements of neutrons from (p,n) reactions in nine target elements; measurement of the angular distribution of fission fragments from proton-induced fission of U233, U225, U228, Th230, and Th232; measurement of alpha-particle angular distributions from (p,α) reactions a study of the neutron-deficient isotopes of terbium and completion of an extensive program of the measurement of activation cross sections. Two more targets for cyclotron production of isotopes were developed, and the production yields for 14 radioisotopes are summarized. A new record for continuous beam power on a production target, 36 kw for 5 hr, was achieved. The design of a beam-deflector system for the 86-in. cyclotron has been completed, and several of the components have been fabricated ; a shutdown for installation is scheduled for October 8. The deflected N+++ beam of the 63-in. cyclotron was used in a study of the gain and loss of electrons by nitrogen lens passing through thin foils, and the equilibrium charge distribution of lens as a function of energy was thus obtained. The excitation functions were measured for nitrogen-induced reactions on both nitrogen and oxygen. Assembly restrictions of the prepared 114-in. heavy-particle cyclotron …
Date:
November 18, 1954
Creator:
Livingston, R. S. & Howard, F. T.
System:
The UNT Digital Library
Possible Use of a Betatron Core on the Cosmotron
Most existing electron synchrotrons use betatron start for initial acceleration of the particles. The subsequent synchrotron acceleration is then performed with a nearly constant radio-frequency. Investigation of the effect of turn-on rate and initial energy spread is made mathematically. Several advantages are seen for such a technique. (D.C.W.)
Date:
January 18, 1962
Creator:
Smith, L. W.
System:
The UNT Digital Library
Once Through Decontamination Studies- Interim Report No. 2
The decontamination of the present Hanford reactors involves a once-through cleaning operation. Considerable interest has been shown in determining the feasibility of this once-through technique for cleanup of certain portions of the NPR system. This is the second interim report of a series that covers tests performed in the 242-B Single Pass Flow Facility. The first was distributed in January, 1960.
Date:
February 18, 1960
Creator:
Hokenson, J. F. & Perrigo, L. D.
System:
The UNT Digital Library
Equations of State for Stream-Water Mixtures and Some Representative Applications Analysis
The majority of two-phase flow problems involving equations of state are solved by use of point-wise utilization steam table values. In this manner, problems involving the use of the various flow equations of continuity, momentum and energy are generally forced into iterative solutions. Considerable effort towards the development of an analytical expression for the state equation seems indicated so as to simplify the analysis of two-phase problems, particularly the transient cases. The question of instability of state and mixture condition is particularly apparent in the analysis of systems undergoing phase transformation as demonstrated by the significant difference between simple theory and experimental critical flow determinations. The assumption of homogeneous, equilibrium mixtures is indicated as a first attack upon the problem.
Date:
April 18, 1960
Creator:
Love, W. J.
System:
The UNT Digital Library
Technical Investigation of Autoclave Failure
On July 31, 1959, an autoclave ruptured while being used for thermal cycling studies of Plutonium Recycle Test Reactor (PRTR) plutonium-aluminum fuel elements. Since stand-in materials were being used in this test, no contamination was involved. This accident could lead to inference of greater hazards associated with PRTR fuel designs than had previously been postulated. An ad hoc technical investigation committee was appointed by the Manager Reactor and Fuels Research and Development, to study the autoclave failure. The committee was charged with developing a sound technical explanation of the accident and/or recommending experimental programs to test hypotheses of the physical and chemical processes leading to the rupture of the autoclave.
Date:
November 18, 1959
Creator:
Wittenbrock, N. G.; Freshley, M. D.; Griggs, B. & Wheeler, R. G.
System:
The UNT Digital Library
Pipet Filler
A number of pipetting aids are commercially available which obviate the necessity of filling pipets by oral suction. Most of the commercially available devices involve fitting the pipet into a soft tight fitting bushing and filling by means of either a piston or a rubber bulb. The pipet is then emptied by means of a valve control which permits, it is claimed, a dispensing accuracy of 0.1mL. It is at once apparent that the probable error (10% for a 1 mL. pipet) is considerably greater than is permissible for great precision. In practice these devices are found to be awkward and after a period of use tend to become even more so due to corrosion of the valve and aging of the rubber bushing and rubber bulbs.
Date:
November 18, 1952
Creator:
Finston, H. L. & Strickland, Gerald
System:
The UNT Digital Library
Initial Experiments on the Brookhaven Reactor. VI. Fast Source Correction for Diffusion Length Measurements on BNL Reactor
In a manner somewhat analogue to that employed by R. Margulies in his memo (BNL Log No. C-2985) on fast source corrections in sigma piles, corrections to be applied to the data obtained on the laid-up graphite in the BNL reactor have been calculated. The correction was computed for a Ra-Be source using the data of Seren and using a standard graphite density for the BNL pile of 1.69. Values of the correction for different experimental sets of data were computed for each of three different diffusion lengths measured parallel to the channels. A correction for diffusion lengths perpendicular to the channels was also determined.
Date:
August 18, 1949
Creator:
Weil, J. W.
System:
The UNT Digital Library
The Separation of Cerium from the Trivalent Rare Earths Using Hydrogen Peroxide and Sodium Acetate
At the present time, cerium-144 and premtheium-147 are the two fission product rare earths that appear most promising for use as the heat source in isotopic power units. Under proper conditions, cerium and the trivalent rare earths can be extracted from the Purex fission product waste stream as an insoluble sodium-rare earth double sulfate. A reprecipitation as the double sulfate, dissolution of the hydroxide, serves to give almost complete separation from the corrosion products, inert constituents of the waste, and from most of the fission products. The cerium and the trivalent rare earths must then be separated from each other. In the case of cerium recovery, it is necessary to remove the trivalent rare earths in order to maximize the specific activity of the cerium. If promethium is the desired product, a preliminary cerium separation is desirable to protect the ion-exchange resin (used for separating promethium from its adjacent rare earths) from the intense high-energy radiation from cerium.
Date:
May 18, 1960
Creator:
Wheelwright, E. J. & Howard, N. C.
System:
The UNT Digital Library
High-Speed Saw Tests Power Reactor Fuels Reprocessing Development
The basic scheme for processing power reactor fuels at Hanford includes the removal of inert endfittings ("hardware") from the active sections of the fuels. Within Hanford Laboratories, research and development studies have been in progress on various types of saws which might be used for hardware cutoff. In the initial phase of the program, high-speed saws were investigated; more recently, studies on low speed saws have been conducted. This report summarizes the high speed saw studies and includes information on abrasive wheels, diamond wheels and metal "friction" blades which cut by actually melting metal ahead of the saw blade. At the completion of the low speed saw testing program currently in progress, basic saw types will be compared and the saw type to be included in the reprocessing complex will be selected.
Date:
November 18, 1959
Creator:
Kelly, V. P.
System:
The UNT Digital Library