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Reactivity Control By Addition Of Neutron Poisons To Slurry Reactors

Description: Calculations show that slurry fueled reactors may be maintained subcritical at arbitrary concentrations and at reactor temperatures above a specified minimum by addition of a soluble neutron poison to the slurry.
Date: December 22, 1959
Creator: Pearson, R. L.; Prince, B. E.; Jeffrey, D. W. & Brassert, W. L.
Partner: UNT Libraries Government Documents Department
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The Concentration of Peroxide in Uranyl Sulfate Solutions at Incipient Precipitation

Description: The concentrations of peroxide in uranyl sulfate solutions at incipient precipitation of uranium peroxide were determined over a temperature interval from 79 to 114'C. The results of the experimental observations have been used to calculate a self-consistent set of numerical parameters that are related to the equilibrium of hydrogen peroxide, uranyl ion and hydrogen ion.
Date: October 22, 1959
Creator: Gilpatrick, L. O.; Jolley, H. R.; Kelly, M. J.; Silverman, M. D. & Watson, G. M.
Partner: UNT Libraries Government Documents Department
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Notes on Heat Transfer in the ORR Core at Powers Greater Than 20 Mw

Description: One of the problems being considered in anticipation of raising the power of the ORR is the possibility of nucleate boiling due to excessive heat fluxes. This note is an attempt to analyze some of the worst conditions of a known core along with extrapolation to higher powers.
Date: September 22, 1959
Creator: Wett, J. F.
Partner: UNT Libraries Government Documents Department
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Programmers Manual: ORACLE Binary Internal Translator (ORBIT) - Algebraic Programming System for the ORACLE

Description: The present edition of the programmers manual for the ORACLE Binary Internal Translator has been completely revised and considerably expanded. At the same time, the Translator program itself has also undergone complete revision. The new version of ORBIT will accommodate programs written in accordance with the original instructions with minor exceptions.
Date: September 22, 1959
Creator: Grau, A. A.; Feliciano, M.; Caldwell, G. C.; Cooper, E. L.; Culkowski, A. & Harrison, J.
Partner: UNT Libraries Government Documents Department
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Internally Cooled Molten-Salt Reactors

Description: 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.
Partner: UNT Libraries Government Documents Department
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Hexone Extraction-Coulometric Titration of Uranium

Description: 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.
Partner: UNT Libraries Government Documents Department
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Report of Fire in Laboratory Hood, Wing I, Building 4500

Description: The fire involved approximately 30 liters of isopropyl alcohol as a result of the ignition of about 16-18 liters of isopropyl alcohol and a slurry of thoria and ammonium nitrate in a 20-liter glass carboy. This material was undergoing a volume reduction by boiling in a floor-type metal hood with Plexiglas sides and 3 sliding door on the front of ordinary glass. The alcohol vapor was vents directly into the hood (Fig1.)
Date: May 22, 1959
Creator: Lain, J. E. & Hungerford, T. W.
Partner: UNT Libraries Government Documents Department
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Preliminary Report on 2% U235-Enriched UF4-C25H52 Critical Assemblies

Description: A series of critical experiments with blocks of 2% U235-enriched UF4-C25H52 has been initiated at the ORNL Critical Experiments Facility. Thus far assemblies with H:U235 atomic ratios of 195 and 294 have been built in parallelepipedal and simulated cylindrical geometries, both reflected and unreflected. From the results the minimum critical masses for reflected spheres have been determined to be 16.3 and 8.5 kg of U235 for fuel mixtures with H:U235 atomic ratios of 195 and 294, respectively. Th… more
Date: April 22, 1959
Creator: Mihalczo, J. T.; Lynn, J.J.; Scott, Dunlap & Connolly, W. C.
Partner: UNT Libraries Government Documents Department
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Control of Thorium Oxide Particle Size

Description: By carefully controlling the agitation, temperature, concentrations, and reagent addition rate, it was possible to produce a thorium oxide product within 0.3 mu of any selected size between 2.0 and 3.0 mu . The rate of addition of oxalic acid to a thorium nitrate solution was the variable used in the current series of tests.
Date: January 22, 1959
Creator: Johnsson, K. O. & Ellison, C. V.
Partner: UNT Libraries Government Documents Department
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Comparison of Fedal Monitor Readings With Radiochemical Sample Data

Description: The purpose of this test is to compare specific isotopic fission product activities with those of the neutron emitters which are monitored by the FEDAL System, and to obtain further information on the source of the unusual activity observed in the PWR reactor coolant.
Date: October 22, 1959
Creator: Jones, Edward
Partner: UNT Libraries Government Documents Department
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Periodic Radiation Survey of Reactor Plant Container and Components After Shutdown "A" Survey

Description: The purpose of this survey is to determine the general area radiation level in the Boiler Compartments using Channel 5 of the Operational Radiation Monitoring System. This report includes the fourth performance test results.
Date: October 22, 1959
Creator: Nelson, Ralph L.; George, John R. & Jones, Edward
Partner: UNT Libraries Government Documents Department
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Control Rod Positions for Criticality

Description: The purpose of this test was to determine critical bank heights and bank worths for various rod configurations at normal Reactor Plant operating temperature and pressure.
Date: October 22, 1959
Creator: Jones, Edward
Partner: UNT Libraries Government Documents Department
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Flat Dispersion Plates Progress Report

Description: The enclosed report covers the work done under the subject contract at the Powder Metallurgy Laboratory, Stevens Institute of Technology, during the period September 1, 1959 through September 30, 1959.
Date: October 22, 1959
Creator: Comestock, Gregory J.
Partner: UNT Libraries Government Documents Department
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Thermodynamic Properties of Carbides at High Temperatures

Description: Thermodynamic properties of the carbide or carbon saturated phases of Ti, Zr, U and Cr are not known accurately. Available data have been summarized by Brewer et al., and some recent measurements have been reported by Chupka and his associates. The purpose of this investigation is to obtain reliable data on the vapor pressures of metals in equilibrium with their carbides by means of graphite Knudsen cells. From the resulting data, the related thermodynamics properties can be calculated.
Date: September 22, 1959
Creator: Fujishiro, S. & Gokcen, N. A.
Partner: UNT Libraries Government Documents Department
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Protection of Carbon Steel from Atmospheric Corrosion

Description: The NPR design calls for carbon steel to be the major constituent in the reactor coolant piping system. The piping and its associated fittings will, in all likelihood, be exposed to atmospheric weather conditions during the period of reactor construction. This type of exposure causes rusting. From experience gained during the startup of KER Loop 1 it is expected that there will be initially high NPR coolant activity levels. The high activity during the startup of KER Loop 1 was partially caused… more
Date: October 22, 1959
Creator: Perrigo, Lyle D., Jr. & Moles, R. G.
Partner: UNT Libraries Government Documents Department
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Soil Column Studies with Radiostrontium I. Effects of Temperature and of Species of Accompanying Ion

Description: Soil chemistry studies have been carried on at Hanford for a number of years in support of the disposal of low and intermediate level liquid wastes to the ground. Equilibrium type experiments were carried out to investigate the mechanisms of the reactions of Sr, Cs, and rare earth ions with soils (1, 3, 4, 5). Experiments were also conducted with simulated and actual wastes in soil columns and an empirical method was developed for prediction of radionuclide breakthrough from ground disposal fac… more
Date: September 22, 1959
Creator: Nelson, J. L.
Partner: UNT Libraries Government Documents Department
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3 Plant Radiation Study Interim Report #5- Part II Data on Gamma Shielding of Special Plutonium Samples

Description: The calculation of shielding the thickness for plutonium is complicated by the many different energies represented in the gamma radiation emitted during decay of the plutonium isotopes. Dose rate predictions are also frequently confused by gamma from varying content of fission product impurities in the plutonium, as well as other gamma radiation induced through alpha and neutron particle absorption within the source material or its environment. After assumptions are made for these many factors… more
Date: October 22, 1959
Creator: Moulthrop, H. A.
Partner: UNT Libraries Government Documents Department
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A Microspark Apparatus for the Study of Inclusions in Metals

Description: A study of metallurgical problems resulting from variation in grain boundaries, bonding layers, and inclusions in metals and alloys has become increasingly important over the past several years. To keep pace with and aid in these studies, several new techniques have been developed in emission and X-ray spectroscopy. In X-ray, areas as smalls as one square micron can be studied by making them targets for a focused electron beam and observing the X-rays emitted (5,2). Such an instrument would be … more
Date: July 22, 1959
Creator: Smith, F. M.
Partner: UNT Libraries Government Documents Department
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The Effect of Solution and Vessel Thermal Expansion on Volume Measurements in the Chemical Processing Department

Description: The major portion of transfers and inventory in the Chemical Processing Department are dependent on volume measurement. Good volume measurements are therefore essential to good SS material control. Considerable attention has been given to the volume problem especially on primary transfer points. Document HW-57888 discusses the biasing effect pf temperature on manometer oil. HW- 57866 given the procedure for vessel calibration. Other undocumented correspondence has discussed recent calibrations … more
Date: May 22, 1959
Creator: Johnson, W. R.
Partner: UNT Libraries Government Documents Department
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Limitations for Existing Storage Tanks for Radioactive Wastes from Separations Plants

Description: Continued process improvements in the separation plants provide an incentive for economics in waste storage costs by utilizing existing facilities to their maximum capability consistent with the radiological hazards involved. The major improvements have reduced waste volumes resulting in increased fission product concentration and energy potential. Analyses have been made to determine the effect of this change on the integrity of the existing structures.
Date: October 22, 1959
Creator: Doud, E.
Partner: UNT Libraries Government Documents Department
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Composition of Solids from Purex LWW

Description: The solids in Purex lww were first observed during flowsheet tests for recovery of fission products from plant wastes. Since the nature of this solid was not apparent from the flowsheet composition of lww, some work was performed to characterize this material. Although this work has been conducted over a period of about one year, it has been subordinate to the main one of testing flowsheets for fission product recovery. The solids have been observed in each of about six samples of plant lww tha… more
Date: January 22, 1959
Creator: Van Tuyl, H.H.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department Monthly Record Report: September 1959

Description: This document details activities of the irradiation processing department during the month of September, 1959. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.
Date: October 22, 1959
Creator: Greninger, A. B.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report, June 1959

Description: Production of Pu from separations plants and output of unfabricated Pu exceeded commitments. Purex plant set a new record high for U processed. Production and shipments of UO{sub 3} met schedules. Purex solvent extraction battery performed below normal, probably because of poor solvent quality. NaOH addition to Redox coating removal waste is being reduced. A 3fold improvement in Recuplex product Al impurity was achieved by means of a specific gravity difference > 0.15 between dilute aqueous fee… more
Date: July 22, 1959
Creator: MacCready, W. K.
Partner: UNT Libraries Government Documents Department
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