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Absorption Spectra of Plutonium and Impurity Ions in Nitric Acid Solution

Description: The absorption spectra for Pu(III), (IV), (VI), and the red Pu(IV)- peroxy complex were determined in HNO/sub 3/ solution. Extinction coefficients for the above species of Pu were measured. Temperature has little effect on the spectra, but variation of acidity causes shifting of absorption peaks and some changes in the extinction coefficients. The absorption spectra and extinction coefficients in the region 390 to 1200 m mu were measured for chromic, nickelous, manganous, calcium, lanthanum, al… more
Date: July 31, 1956
Creator: Myers, M. N.
Partner: UNT Libraries Government Documents Department

[Advertising Star-Telegram slides]

Description: Photograph of a slide with messages that reads, "Total circulation over 225,000 Fort Worth Star-Telegram," and "Serving 138 Texas counties." In the center to the right, there is a Texas state logo for the Texas Ranch and Farm. The slide is taped to a light-colored wall.
Date: July 31, 1952
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Partner: UNT Libraries Special Collections

[Advertising Star Telegrams Farm Journal]

Description: Photograph of a slide that reads "Star-Telegram's monthly Farm Magazine largest circulation in Texas." The illustration on the left showcase the cover of a book that reads "Fort Worth Star-Telegram. Delivered to 100,000 Ranchers and Farmers. 1st Sunday each month." Included, there is a logo for the Texas Ranch and Farm.
Date: July 31, 1952
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Partner: UNT Libraries Special Collections
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Beryllia and Beryllia-Beryllium Bodies for Moderating Cores in Fuel Elements

Description: From introduction: This report presents the results of the two phases of the work: study of the compatibility of beryllia bodies with a coating material, molybdenum; and studies of beryllia-beryllium body fabrication.
Date: July 31, 1952
Creator: Long, R. E.; Duckworth, W. H.; Saller, Henry A.; Stacy, J. T.; Miller, R. A. & Schofield, H. Z.
Partner: UNT Libraries Government Documents Department
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A CALCULATION OF THE GAMMA-RAY SPECTRUM OF THE BULK SHIELDING REACTOR

Description: A calculation was performed to determine the highenergy portion of the gamma-ray flux at the surfacc of the uranium-aluminum BSF reactor. The flux was considered to consist entirely of the uncollided flux plus the Comptonscattered flux. The four sources of primary gamma rays included in the calculation were prompt fission gamma rays, capture gamma rays from aluminum, capture gamma rays from uranium, and fission-product decay gamma rays. These sources were divided into four energy groups. Althou… more
Date: July 31, 1957
Creator: deSaussure, G.
Partner: UNT Libraries Government Documents Department
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Chemical development Separations Technology Unit. Progress report

Description: The Redox Plant operated at a 76.7% time efficiency (IAF basis) and averaged 3.16 tons of uranium per operating day during the month. During the period from July 4 through July 13, 38,000 gallons of 72% ANN from Tygon-lined storage tank SS-112 were used in aqueous salt solution make-ups with some emulsion difficulty and fission-product carry-over resulting. New ANN, from stainless-steel tanks, was used for the balance of the month. An extensive (thermally) hot 60% HNO{sub 3} cleanout was given … more
Date: July 31, 1952
Creator: Woodfield, F. W.
Partner: UNT Libraries Government Documents Department
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The Dependency of Reactivity of Burn-up in Fast Reactors

Description: In fast reactors the poisoning effects of fission products are reduced because of relative low capture cross sections at high energies. In addition, in fluid fuel reactors there is the possibiity of removing them by processing. If plutonium production is of secondary importance to power production, then higher burnup of fuel is possible and dependency of reactivity on burnup becomes a problem of interest. One-group calculations are performed as a first step in understanding the relative effe… more
Date: July 31, 1953
Creator: Sehnert, R. H.
Partner: UNT Libraries Government Documents Department
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Development of Uranium Nitride-Stainless Steel Dispersion Fuel Elements

Description: In research in support of the GCRE, procedures for the fabrication of stainless steel-clad flat-plate fuel elements having a core of 28 w/o UN dispersed in an iron-18 w/o chromium--14 w/o nickel--2.5 w/o molybdenum matrix were developed. The preparation of UN and its compatibility with the components of the matrix alloy were studied. The UN for the program was prepared by nitriding uranium metal at 850 C and then dissociating the U/sub 2/N/sub 3/ produced to UN in a vacuum at 1300 C. In compati… more
Date: July 31, 1959
Creator: Paprocki, S. J.; Keller, D. L.; Cunningham, G. W. & Foulds Jr., A. K.
Partner: UNT Libraries Government Documents Department
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Experimental Investigation of Flutter and Divergence Characteristics of the Rocket-Motor Fin of the ASROC Missile

Description: Report presenting testing of models of rocket-motor fins of the ASROC missile for flutter and divergence in the supersonic flutter tunnel for a range of Mach numbers. Results indicate that both divergence of the overhung leading edge and flutter occur within the sea-level operating conditions of the missile at Mach numbers above 1.0. Results regarding the flutter boundary, type of flutter encountered, possible solutions to flutter problems, and possible effects of nondestructive type of flutter… more
Date: July 31, 1958
Creator: Levey, Gilbert M. & Hanson, Perry W.
Partner: UNT Libraries Government Documents Department
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Experimental investigation of flutter and divergence characteristics of the rocket-motor fin of the ASROC missile: COORD. No. N-AM-66

Description: Report presenting testing of scale models of rocket-motor fins of the ASROC missile for flutter and divergence in the supersonic flutter tunnel over a range of Mach numbers. Results regarding the flutter boundary, type of flutter encountered, and effects of flutter are provided.
Date: July 31, 1958
Creator: Levey, Gilbert M. & Hanson, Perry W.
Partner: UNT Libraries Government Documents Department
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Final Report on Purification of Thorium Nitrate by Solvent Extraction With Tributyl Phosphate: 1. Laboratory Investigations

Description: Report discussing laboratory investigations of thorium nitrate purification. Batch equilibrium data, solubility data, viscosity data, density data, and the results seven batch countercurrent extraction tests and two selective stripping tests are included.
Date: July 31, 1952
Creator: Ewing, R. A.; Fishel, J. B.; Kiehl, S. J., Jr.; Sharpe, R. E. & Bearse, A. E.
Partner: UNT Libraries Government Documents Department
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Final Report on Purification of Thorium Nitrate by Solvent Extraction With Tributyl Phosphate: 2. Mixer-Settler Pilot Plant Investigations

Description: From abstract: "This report describes the construction and operation of a mixer-settler pilot plant for the purification of mantle-grade thorium nitrate. The liquid-liquid extraction process utilized 30% tributyl phosphate - 70% 'Solvesso-100' as the organic solvent and nitric acid as the salting agent. Continuous steady-state operation of the equipment was demonstrated, with very good recovery of thorium."
Date: July 31, 1952
Creator: Burkhart, C. A.; Foley, D. D.; Retzke, F. A.; Filbert, Robert B., Jr. & Clegg, John W.
Partner: UNT Libraries Government Documents Department
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Gas Cooled Nuclear Reactor Study

Description: Study of a gas cooled reactor with design specifications providing for a source of high temperature heat to a stream of helium. This reactor, in turn, is used as a source of heat for the air stream in a gas-turbine power plant.
Date: July 31, 1956
Creator: Thompson, A. S.
Partner: UNT Libraries Government Documents Department
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Gas Cooled Nuclear Reactor Study. Final Report

Description: An investigntion was made of the performance of a gas-cooled reactor, designed to provide a source of high temperature heat to a stream of helium. This reactor, in turn, is used as a source of heat for the air stream in a gas- turbine power plant. The reactor design was predicted primarily on the requirement for transferring a large amount of heat to the helium stream with a pressure drop low enough that it will not represent a major loss of power in the power plant. The mass of uranium e uired… more
Date: July 31, 1956
Creator: Thompson, A. S.
Partner: UNT Libraries Government Documents Department
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