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Atomic Energy Commission Reports
208
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81
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71
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64
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Effect of Quadrupole Lenses
"The effect of correcting quadrupole lenses on the betatron oscillation characteristics of an AG synchrotron was studied, and general formulas are given for the fractional changes of the amplitude and phase functions. Calculations performed for different setups of different numbers of lenses for the CEA synchrotron structure point out that one may correct for sizable errors in the n- value by means of 8 pairs of quadrupole lenses in two consecutive straight sections with the focusing lens between defocusing sectors and vice versa. An increase of BETA /sub max/ of about 5% is obtained for DELTA n/n approximately 0.04. It was found that the necessary corrections can probably be obtained satisfactorily with lenses of 6 in. length. "
Date:
June 3, 1957
Creator:
Lanza, G. & Steffen, Klaus G.
Object Type:
Report
System:
The UNT Digital Library
Pole-Face Windings
"A summary is presented of a preliminary study of the application of pole- face windings to the Cambridge Electron Accelerator. Estimates are made of the currents required, the forces on the wibdings and the voltages induced by the magnetic flux. The possibility of automatic control of the pole-face currents in explored, and feasible control systems are suggested."
Date:
June 20, 1957
Creator:
Rees, John
Object Type:
Report
System:
The UNT Digital Library
Off-Site Animal Investigation Report : Second Annual Report
Since the inauguration of the Off-Site Animal Investigation project n 1957, there has been one annual report rendered as of 30 June 1958. this is the second annual report dated as of 30 June 1959. The objectives of the project have been unchanged during the past year. These are (1) to enhance the Nevada Test Site/off-site rancher relationship through an active investigation project in their interests, and (2) to provide further information as to the status of the off-site animals in their environment, with special emphasis on their radioactive isotope uptake from fall-out. isotope uptake of the animals is being emphasized as well as the gross and microscopic histopathological examinations. Two year's existence in an area of radio-contamination where a full fission spectrum of isotopes can be found, where radiation background reading range from 1/2 mr per hour to 1 = per hour, has produced no noticeable effect on the animals.
Date:
June 30, 1959
Creator:
Farmer, Garland F.
Object Type:
Report
System:
The UNT Digital Library
Diffusion in a Temperature Gradient
To summarize one finds that for diffusion in a temperature gradient by a vacancy mechanism one must have E(M) < E(F). No such restrictions occur for interstitial diffusion. The spatial vacancy distribution is very nearly the equilibrium distribution if dislocations are present. If no dislocations are present then one could obtain E(M) by measurement of the spatial distribution.
Date:
June 1959
Creator:
Koehler, James S. (James Stark), 1914-2006
Object Type:
Report
System:
The UNT Digital Library
A Non-Destructive Test for the Identification of Cadmium Plating
A simple non-destructive chemical method for the identification of cadmium plating is presented. The test requires no special techniques or equipment and may be conducted in less than fifteen seconds.
Date:
June 26, 1953
Creator:
Leslie, W. B.
Object Type:
Report
System:
The UNT Digital Library
The Effect of Crystallite Size on the Bulk Density and Strength Properties of Uranium Dioxide Specimens
Fused uranium dioxide was separated into fractions of varying particle size by air separation. Specimens of the nominal size of 1/8 by 1/4 by 1½ in. were formed by hydrostatic pressing, firing, and lapping. Specimens prepared from the 0 to 5 μ fraction were the strongest and most dense. The room-temperature density was about 92% of theoretical and the room-temperature flexural strength was about 12,000 1b. per sq. in. When tested at 1000°C., the strength was about 18,000 1b. per sq. in. The flexural strength of specimens decreased and their density decreased as the starting particle size was increased. The crystallization of the urania fragments which had occurred during the firing treatment was observed.
Date:
June 1, 1955
Creator:
Burdick, Milton D. & Parker, H. S.
Object Type:
Report
System:
The UNT Digital Library
Effects of Ultraviolet Radiation on Chloroplast Reactions and Plant Metabolism
This technical report represents a brief survey of work by this project on the effects of ultraviolet radiation (UV) on certain of the photochemical and metabolic properties of rhubarb chard and sugar beet (Beta vulgaris). These plants were selected for this work because for some years they have been used as sources of chloroplasts for Hill reaction studies in this laboratory. Some of this work has appeared as a brief paper.
Date:
June 15, 1955
Creator:
Anderson, Donald R.; Spikes, John D. & Mayne, Berger C.
Object Type:
Report
System:
The UNT Digital Library
Fundamental Research in Nuclear Spectroscopy and X-Rays. Annual Report No. 1 for Period October 1, 1954 to September 30, 1955 on Research in Precision Spectroscopy of Nuclear Energy Levels
The primary purpose of this contract is to develop and exploit techniques for the precision measurement of nuclear energy levels by the spectroscopic study of gamma-rays emitted during the decay of radioisotopes, (1) by the use of a high resolving power curved crystal focusing spectrometer to study wavelengths and intensities of gamma-rays themselves, (2) by means of a precision beta-ray spectrometer to study the conversion lines from gamma-rays both by internal conversion and with external converters.
Date:
June 1955
Creator:
DuMond, Jesse W. M. (Jesse William Monroe), 1892-1976
Object Type:
Report
System:
The UNT Digital Library
Reaction of Graphic with Sodium
Most of the publications in the open literature available to us agree that sodium does not readily react with graphite, though potassium, rubidium, and cesium readily enter between the planes of the graphite lattice. In view of the conflicting evidence available, it seems inadvisable without very extensive further study to consider the use of graphite in direct contact with liquid sodium, except under very mild conditions of temperature and irradiation, and then only with very pure sodium and completely graphitized graphite.
Date:
June 19, 1952
Creator:
Montet, G. L.
Object Type:
Report
System:
The UNT Digital Library
Chemical Development Section C Progress Report for December 1960 and January 1961
Test work was completed on development of a stripping method for the amine extraction (Amex) process which produces a concentrated uranyl nitrate solution for shipment to the refinery. This procedure offers potential cost savings by simplifying the overall mill-refinery flowsheet. The process involves treatment of the amine extract with calcium nitrate solution to convert the uranium in the solvent to a nitrate complex, stripping the uranium with water or dilute nitric acid, and recovery of nitrate from the solvent for recycle by contact with a lime slurry.
Date:
June 2, 1961
Creator:
Brown, K. B.
Object Type:
Report
System:
The UNT Digital Library
Spectrophotometric Determination of Microgram Quantities of Osmium With Diphenylcarbazide by G. Goldstein
A method was developed for the spectrophotometric determination of 30 to 100 ug of osmium as OSO4 is extracted with CHCl3 and diphenylcarbazide is then added to the organic extract. A blue-violet reaction product is formed, the absorbancy of which is measured at 560 mu. A suitable reagent concentration is from 3 to 5 ml of 0.2% diphenylcarbazide in a volume of 25 ml and the preferred solvent for the reagent is ethanol. Beer's law is followed over a range of 8 to 130 ug of osmium with a coefficient of variation of about 4%. After a 2-hour color-development period the molar absorbancy in less than 2 hours were unsuccessful. A study was made of the effects of foreign elements and only Ru(VIII) was found to interfere.
Date:
June 2, 1959
Creator:
Menis, Oscar
Object Type:
Report
System:
The UNT Digital Library
Uranium Anion Exchange Equilibria on Dowex 21K
Equilibrium loading of uranium on Dowex 21K has been studied in a sulfate system for uranium concentrations from 0.0005 M to 0.0005 M, total sulfate concentrations of 0.45 M to 0.6M, and sulfuric acid concentration of 0.020 M. Loading data have been fitted to Langmuir adsorption isotherms and Langmuir constants have been evaluated. Resin was equilibrated with uranium feed solutions by flowing the feed through a shallow fixed bed of resin.
Date:
June 29, 1959
Creator:
Dunn, W. E.
Object Type:
Report
System:
The UNT Digital Library
Solids Accumulation and Fission Heating in the HRT Chemical Plant Underflow Pot (Co-op Report, Fall Quarter, 1958)
The purpose of this study was to develop equations for calculating fision product heating in the HRT-CP underflow pot from measured temperatures and to attempt to correlate the rat of solids accumulation in the underflow pot with fission heating and reactor power. Using fission heating data calculated from relating solids accumulation and heating have been tested. In one case an error of no greater than 26% was incurred in the calculation of the total weight of solids collected during chemical plant runs 17-4, 17-5, and 17-6. Further development work will be done on this correlation.
Date:
June 10, 1959
Creator:
Dunn, W. E.
Object Type:
Report
System:
The UNT Digital Library
Theoretical Study of Single-Transfer Line Concatenated Pulse Column Systems
Calculations indicate that single-transfer line concatenated pulse column systems can be operated with static pressures that are not excessive if a sufficient number of vessels are employed in the system. The required number of vessels can be attained by using a series of short columns or by using holdup pots in conjunction with a limited number of columns.
Date:
June 19, 1959
Creator:
Johnson, H. F.
Object Type:
Report
System:
The UNT Digital Library
Estimate of Potential Fuel Reprocessing Revision #28 - Part A
The power and estimated reprocessing load are tabulated for existing and proposed United States and United States-built reactors of 10 Kw or greater thermal power.
Date:
June 25, 1959
Creator:
Ullmann, J. W.
Object Type:
Report
System:
The UNT Digital Library
Corrosion Status: Sulfex-Thorex (Ni-o-nel) and Darex-Thorex (Titanium) as of June 12, 1959
Either system appears to be fairly satisfactory from a containment standpoint. Current results indicate probable over-all rates of about 0.2mils/mo for titanium vs. 1.5-3.0 mils/mo for Ni-o-nel. Tests are not 100% comparable due to changes made in flowsheet conditions, but have been of sufficient variation and length as to allow good predictions to be made. Both metals show some tendency toward local attack in Thorex solutions. These tendencies are increased by poor welding techniques.
Date:
June 29, 1959
Creator:
Clark, W. E.
Object Type:
Report
System:
The UNT Digital Library
Lecture Notes on Reactor Controls
This course on reactor controls is for the purpose of acquainting the student with some of the elementary considerations involved in setting up a control and safety system for a nuclear reactor. This material is the outgrowth of the notes prepared for the lectures on Reactor Controls given in the Oak Ridge School of Reactor Technologu. The lectures given by T. E. Cole in 1953-1955 are the basis of portions of the subject matter on reactor kinetics. Many suggestions and ideas contributed by E. R. Mann are included throughout almost every section. In addition, several members of the Oak Ridge National Laboratory, and of the Reactor Controls Department in particular, have provided information which has been included in these lectures notes.
Date:
June 24, 1959
Creator:
Walker, C. S.
Object Type:
Report
System:
The UNT Digital Library
Summary of HRT Run 14
This report presents a detailed study of HRT Run 14, which was abruptly terminated by the formation of a hole in the Zircaloy-2 core tank. In this run the reactor was operated at high temperature and pressure for ten days from March 25 to April 4, 1958. Nuclear power operation extended from March 29 until April 4, when fuel solution leaked into the heavy-water blanket. The maximum power level attained was 6.4 Mw.
Date:
June 8, 1959
Creator:
Engel, J. R.; Haubenreich, P. N.; Kolb, J. O. & Richardson, D. M.
Object Type:
Report
System:
The UNT Digital Library
Internally Cooled Molten-Salt Reactors
The initial and long-term nuclear characteristics of two internally cooled heterogeneous, graphite-moderated, two-region, molten-salt reactors have been studied. These reactors have doubling times of 22.5 years and 27.5 years. Methods of decreasing the doubling times by removing the Pa233 from the core and be increasing the specific power of the reactor are described.
Date:
June 22, 1959
Creator:
Lackey, M. E.
Object Type:
Report
System:
The UNT Digital Library
Fuel Cycle Cost for Aqueous Homogeneous Reactors
By using a large central fuel and blanket reprocessing facility, slurry-fueled aqueous homogeneous reactors can attain an estimated minimum fuel cycle cost of 1.4-1.6 mills/kwh; with solution-fueled two-region reactors, a doubling time of 14 years may be obtained at a fuel cycle cost of 2.0 mills/kwh. On-site processing appears desirable only for large power stations made up of reactors designed for short doubling times. For instance, a solution-fueled two-region reactor can attain a 12-year doubling time at an estimated fuel cycle cost of 1.5 mills/kwh at a 2000 Mw electricity station with an on-site processing plant.
Date:
June 2, 1959
Creator:
Culler, F. L.
Object Type:
Report
System:
The UNT Digital Library
Hexone Extraction-Coulometric Titration of Uranium
Samples containing 5 to 10 mg of uranium were extracted with hexone (methyl isobutyl ketone) and titrated coulometrically in sulphate media. Relative standard deviations of 0.45% for samples containing 5 mg and 0.56% for 10 mg were determined by precision studies.
Date:
June 22, 1959
Creator:
Blevins, E. L.
Object Type:
Report
System:
The UNT Digital Library
Status and Future Program of Homogeneous Reactor Fuel Processing Studies
The behavior of insoluble corrosion products in the HRT is generally understood and studies of the removal of these solids by hydroclones can logically be terminated after the effect of higher processing rates by the multiple hydroclone has been determined. Chemical descaling may be required to supplement solids removal by hydroclones. Laboratory studies to find suitable reagents will be continued in conjunction with decontamination work presently in progress.
Date:
June 17, 1959
Creator:
Burch, W. D.; Haas, P. A. & McNees, R. A.
Object Type:
Report
System:
The UNT Digital Library
Power Reactor Fuel Reprocessing Process Wastes
Data on waste volumes and heat generation of several reactor fuels which may be reprocessed in the Power Reactor Fuel Reprocessing Pilot Plant at ORNL are tabulated.
Date:
June 19, 1959
Creator:
Irvine, A. R.
Object Type:
Report
System:
The UNT Digital Library
Status Report- Application of Electroless-Nickel Brazing to Tabular Fuel Elements for the N. S. Savannah
The feasibility of using electroless nickel, a chemical deposit containing about 10 wt% phosphorous in nickel, as the brazing alloy for assembling tubular stainless steel fuel elements of the type specified in Core I of the N. S. Savannah was investigated. This material was nelected primarily because of the case of braze-metal preplacement by chemical deposition of the alloy on type 304 stainless steel ferrule spacers, prior to fuel-bundle assembly. Brazed joints produced by this method were generally characterized by a relatively ductile solid-solution region at the thinnest portions of the fillet. This ductile zone should minimize the possibility of complete propagation of hairline cracks, which form in the brittle, eutectic regions of fillet.
Date:
June 2, 1959
Creator:
Lamartine, J. T. & Thurber, W. C.
Object Type:
Report
System:
The UNT Digital Library