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Monex Process: Terminal Report

Description: Chemical and engineering data were obtained for the feed digestion system and the extraction-scrub step of the Monex tributyl phosphate solvent-extraction process for recovering thorium and uranium from nitric acid-digested unclarified monasite sludge. Tests of the recommended conditions in a 2-in.-dia pulsed column demonstrated that thorium losses were approximately 1.2% and uranium losses, 1.5%. The flowsheet is workable but is not necessarily optimum.
Date: January 31, 1958
Creator: McNamee, R.J. & Wischow, R.P.
Partner: UNT Libraries Government Documents Department
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Aircraft Reactor Test Hazards Summary Report

Description: The successful completion of a program of experiments, including the Aircraft Reactor Experiment (ARE), has demonstrated the high probability of producing militarily useful aircraft nuclear power plants employing reflector-moderated circulating-fuel reactors. Consequently, and accelerated program culminating in operation of the Aircraft Reactor Test (ART) is under way. In order to adhere to the compressed schedule of the accelerated program, it is essential that the Atomic Energy Commission approve the 7500 Area in Oak Ridge as the test site by February15, 1955. This report summarizes the hazards associated with operating the contained 60-Mv reactor of the ART at the proposed Oak Ridge test site.
Date: January 19, 1955
Creator: Cottrell, W.B.; Ergen, W.K.; Fraas, A.P.; McQuilkin, F.R. & Meem, J.L.
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Test Summary Report for the Advisory Committee on Reactor Safeguards

Description: The Homogeneous Reactor Test (HRT) is the experimental reactor facility (Frontispiece) being designed and constructed at ORNL as the next step in homogeneous reactor development between the 1-Mv HRE and a "full-scale" power station. The HRT will provide an integrated test at 5 to 10 Mv for the flowsheet and equipment designs on which the full-scale effort will be based. Furthermore, its design is such that several homogeneous systems which require essentially the same operating equipment may be tested with comparatively minor modifications of the original reactor installation. The reactor will be assembled in the building which housed the HRE, located in the experimental reactor exclusion area approximately one mile south of the oak ridge laboratory. (See figure 1) / It is the purpose of this report to provide information with which the hazardous aspects of this reactor may be evaluated. Briefly, it will be shown after a statement of purpose and a general description of the reactor that: 1. The design characteristics and equipment requirements are such that escape of highly reactive material from the reactor piping is unlikely. 2. Should the entire core and blanket contents suddenly escape from the reactor system, a seal-welded steel tank surrounding the system will prevent the leakage of a significant quantity of activity into the building. The biological hazards resulting from the destruction of the reactor and shield by bombing or other remote causes are presented in detail.
Date: January 5, 1955
Creator: Beall, S.E. & Visner, S.
Partner: UNT Libraries Government Documents Department
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A Cost Analysis of the Idaho Chemical Processing Plant

Description: A capital cost breakdown of the Idaho Chemical Processing Plant, a directly maintained remotely operated plant for processing spent enriched uranium fuel assemblies from reactors, is presented. The capital investment in the plant, including design, construction, training, and preoperational costs, an estimate of the direct costs incurred by the Atomic Energy Commission, and a proportional part of the costs of Central Facilities, including the value of the land and improvements theorem when acquired by the Commision, was $31,105,899. The cost of design and construction was $25,212,231, of which $3,773,357 was expanded on design and inspection.
Date: January 4, 1955
Creator: Robertson, P.L. & Stockdale, W.G.
Partner: UNT Libraries Government Documents Department
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Chain Reaction of Pure Fissionable Materials in Solution

Description: The critical mass of 94-239 and the corresponding critical dimensions of homogeneous mixtures of 94-239 with various moderating media been calculated as a function of the concentration of 94. A simple transformation makes the figures applicated to92-235. the results are in essential agreement with the preliminary estimated made independently by Oppenheimer and Serber. The problem of the stability of a chain reaction in solution and questions of protection are discussed.
Date: January 1, 1943
Creator: Christy, Robert F., 1916-2012 & Wheeler, John Archibald, 1911-2008
Partner: UNT Libraries Government Documents Department
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The Thermal Decomposition of Uranium Mononitride

Description: The use of uranium mononitride as a nuclear fuel is being considered for a number of high temperature applications. In comparison with the most often applied high temperature fuels, UO2 and UC, one finds that UN has a combination of the high melting point of UO2 and the thermal conductivity and high uranium density of UC. However, interest in UN is often dampened by qualitative indications of its low thermal stability and by lack of experimental thermodynamic data. Is is the purpose of this study, therefore, to provide a quantitative measure of the thermal stability of UN and to establish some of its thermodynamic properties.
Date: January 7, 1964
Creator: Vozzella, P. A.; Miller, A. D. & DeCrescente, M. A. (Michael A.)
Partner: UNT Libraries Government Documents Department
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Engineering Report on the Design of the Pratt & Whitney Aircraft Forced Convection Alkali Metal Vaporization Condensation Heat Transfer Rig

Description: Summary. A test rig has been designed to obtain basic two phase forced convection liquid metal heat transfer and pressure drop data for use in the design of liquid metal boilers. This engineering report includes background of the boiling problem, partial summary of work done by other investigators, the object, scope, engineering, and operations of this test rig, and a summary of reproducibility tests conducted in a water back-up rig.
Date: January 18, 1963
Creator: Bernstein, E.
Partner: UNT Libraries Government Documents Department
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Spinning of Columbium & Columbium 1%- Zirconium Tubing

Description: The following objectives were planned for this project. (1) Development of spinning data necessary for spinning Columbium and Columbium-1% Zirconium tubing from ingot, forged or welded tube blanks. (2) Determine mechanical & metallurgical properties of spun Columbium and Columbium-1% Zirconium tubing. (3) Determine dimensional and tolerance limits possible to attain on spun Columbium and Columbium-1% Zirconium tubing based on our present equipment, tooling limitations, and the spinning tests performed for objective No. 1.
Date: January 19, 1961
Creator: Barker, Wharton R.
Partner: UNT Libraries Government Documents Department
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An Analysis of Inconsistencies in Removal Cross Sections of Carbon and Oxygen

Description: Abstract. Some recent analysis of certain Lid Tank fast neutron dose rates measured in oil and water indicates that there are some basic inconsistencies with reported oxygen and carbon removal cross sections and the reported data. These inconsistencies may be explained in several ways: (1) The reported carbon removal cross section is wrong. (2) The reported oil composition is wrong. (3) The reported oxygen removal cross section is wrong since it is based on an assumed rather than a measured oil composition. (4) Some of the experimental data are wrong. It is not possible to determine which of the above is most likely on the basis of analysis alone but the possibilities are pointed out and, based on the assumption that all the experimental data are correct, it appears most likely that the oil composition assumed in ORNL 2197 was in error.
Date: January 20, 1961
Creator: {{{name}}}
Partner: UNT Libraries Government Documents Department
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Column Adsorption Methods in Analytical Chemistry

Description: Technical report. Numerous application of various column adsorption techniques to inorganic analytical chemistry have appear in the literature. The comparatively recent introduction of ion exchange resins has resulted in the development of efficient, simple, and rapid column adsorption methods. the principal service of column adsorption methods to analytical chemistry is that of providing a relatively simple means of separating an element in a sufficiently pure state so that a direct precipitation, ignition, and weighting, for example, will suffice to complete the quantitative analysis. Systems involving uranyl nitrate will naturally be emphasized in this report but information will be included concerning the separation of the individual members of a series from one another, such as in the alkaline earths and the rare earths.
Date: January 11, 1946
Creator: Schubert, Jack
Partner: UNT Libraries Government Documents Department
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Preliminary Report on a Colorimetric Method for the Determination of Microgram Quantities of Thorium : Experiments in the Dissolution of O2 Metal [UO2]

Description: Abstract. thorium can be precipitated as a salt of p-dimethylaminoazophenylarsonic acid at a pH of about 1.5. the precipitate, collected on a sintered glass filter is washed with dilute ammonium hydroxide to dissolve the dye. the amount of thorium is determined by measuring the concentration of the dye spectrophotometrically at a wavelength of 450 millimicrons. Zirconium, which interferes, can be separated and determined using the same reagent in strong hydrochloric. the behavior of thorium metal upon treatment with various acids and upon fusion withKHSO4 is described. three satisfactory procedures are given for dissolving the metal with sulfuric acid, phosphoric acid, and by a potassium hydrogen sulfate fusion. The laboratory was presented with the problem of analyzing for a large number of elements in O2 metal. the results of a systematic study of methods for effecting solution of the metal are offered here since they may be of some interest and use to other laboratories. The four methods which effected complete solution of the metal are (1) Sulfuric acid method; (2) Fusion method; (3) Phosphoric acid method; and (4) Nitric acid-hydrofluoric acid method.
Date: January 1, 1945
Creator: Byerly, W.; Niedrach, L.; Davin, W.; Dyas, H. & Bane, R. W.
Partner: UNT Libraries Government Documents Department
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Transference and Adsorption on Glass of Carrier Free Zirconium

Description: .Technical report describing the transference experiments. The carrying of zirconium and columbium by ferric hydroxide has a very marked dependence on pH. In the experiments it was noticed that the concentration of Zr activity in various solutions changed with time This indicated that the Zr was being adsorbed on the glass. The carrier free trace is adsorbed on glass. This effect must be considered in experiments with Zr tracer in glass apparatus.
Date: January 3, 1945
Creator: Dodgen, H. W. & Rollefson, G. F.
Partner: UNT Libraries Government Documents Department
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The Effect of Impurities Upon Sulfide Refractories

Description: Abstract. A summary of the effect of metal, carbon, silicon, and oxygen impurities upon the various sulfide refractories is given and the proper procedures for elimination of the impurities are discussed. CeS which is properly prepared can be handled in air without danger of catching fire or appreciable oxidation. 650 satisfactory crucibles have been made to date using sulfides which were screened and pressed in air with less than 0.5% oxygen pickup. The other cerium and thorium sulfides are even more inert to oxidation than is CeS. Phase diagram possibilities are discussed for the cerium and thorium sulfide and oxy-sulfide systems. Further study of the ThS has shown that ThS crucibles are the highest melting and least volatile of the sulfide crucibles and ThS may be used for remelting of some metals up to 2000 degrees C. ThS crucibles appear to be the most suitable containers for metal reductions.
Date: January 20, 1945
Creator: Brewer, L.; Bromley, L. A.; Gilles, P. & Lofgren, N.
Partner: UNT Libraries Government Documents Department
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Process Engineering Report on Production of Thorium at Iowa State College

Description: Technical report presenting the results of a study of the AEC thorium production facilities at Iowa State College, Ames, Iowa. Operating procedures, descriptions of equipment and a production cost analysis have been included in this study.
Date: January 16, 1952
Creator: Bulkowski, H. H.; Holby, G. V.; Pfeiffer, C.; Maerker, J. B. & Winn, F. W.
Partner: UNT Libraries Government Documents Department
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Process Engineering Report on Thorium Semi-Works Plant for the Feed Materials Production Center - Fernald, Ohio, Job No. 3542

Description: This technical report presents the process design for the thorium semi-works plant which will be located at the Feed Materials Production Center, Fernald, Ohio. It contains the process information required for the layout and detailed mechanical design of the thorium plant.
Date: January 31, 1952
Creator: Bulkowski, H. H.; Delaplaine, J. W.; Holby, G. V.; Natale, N. R.; Reiter, W. M. & Roe, B. J.
Partner: UNT Libraries Government Documents Department
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Removal of Deuterated Boric Acid From Deuterium Oxide Solution by Ion Exchange Resin

Description: Introduction: "Because of the importance of the value of the transport mean free path of thermal neutrons in deuterium oxide, Kash and Woods proposed to redetermine this value in deuterium oxide (99.4 atom-percent deuterium, by an extrapolation method. Kash and Woods thought that the low value of the transport mean free path might be a source of error. This paper relates studies of procedures by which (1) boron material would be dissolved in high content deuterium oxide without adding foreign atoms, particularly hydrogen atoms which might adversely affect the test, (2) the boron content of the deuterium oxide solvent may be determined, (3) ion exchangers may be deuterized and de-deuterized, and (4) ion exchange may remove specific ions from solution."
Date: 1954-01-5
Creator: Silverman, L.
Partner: UNT Libraries Government Documents Department
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Sodium Graphite Reactor, Quarterly Progress Report, June-August 1953

Description: "Engineering was continued on the development of sodium cooled, graphite moderated type reactors. General studies were carried out as well as studies specifically devoted to the following: a. full scale poser-only plant, b. thirty-mega watt pilot plant, the SGR, c. sodium reactor experiment, the SRE. This work consisted of theoretical analysis of various aspects of nuclear performance; economic investigations of different fuel element, cooling system and plant arrangements; and experimental investigations related to the properties of certain materials and to the development of components. Preliminary consideration was given to alternative reactor arrangements employing liquid hydrocarbon moderators and high temperature coolants other than sodium. In addition to a summary of the general design features of the SRD, a program was prepared outlining the proposed use of this installation.
Date: January 20, 1954
Creator: Inman, G. M.
Partner: UNT Libraries Government Documents Department
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The Synthetic Liquid Fuel Potential of Texas

Description: Report documenting the suitability of Texas for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest.
Date: January 25, 1952
Creator: Ford, Bacon, and Davis
Partner: UNT Libraries Government Documents Department
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The Synthetic Liquid Fuel Potential of West Virginia

Description: Report documenting the suitability of West Virginia for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest.
Date: January 31, 1952
Creator: Ford, Bacon, and Davis
Partner: UNT Libraries Government Documents Department
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A summary interpretation of geologic, hydrologic, and geophysical data for Yucca Valley, Nevada test site, Nye County, Nevada

Description: "This report summarizes an interpretation of the geology of Yucca Valley to depths of about 2,300 feet below the surface, the characteristic features of groundwater in Yucca and Frenchman Valleys."
Date: January 1959
Creator: Wilmarth, V. R.; Healey, D. L.; Clebsch, Alfred; Winograd, Isaac J.; Zietz, Isidore & Oliver, Howard W.
Partner: UNT Libraries Government Documents Department
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The Synthetic Liquid Fuel Potential of Ohio

Description: Report documenting the suitability of Ohio for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest
Date: January 29, 1951
Creator: Ford, Bacon, and Davis
Partner: UNT Libraries Government Documents Department
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