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Utilization of Radiactive Isotpoes in Coal Process Research

Description: "This is the third quarterly report on Task II dealing with Methods Development for Radio-Tracing of Coal Product Hydrocarbons With Tritium. The problem of accurate low-level tritium assay for tagged hydrocarbons has been resolved and attention is now primarily directed at the questions of tritium mobility and radio-chemical purity in tagged tracers."
Date: February 15, 1961
Creator: Yavorsky, P. M. & Gorin, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Utilization of Radiactive Isotpoes in Coal Process Research

Description: "With careful attention to details, tritium assays of satisfactory accuracy have been achieved on low activity standard samples by dry combustion and liquid scintillations counting of the product water.This method is faster, more accurate and dependable than the zinc fusion-ion chamber method fro low level tritium assays. At 380 degrees C, tritium loses from hydrocarbon tracers by isotopic exchange is significant and must be corrected for in tracer measurements at this elevated temperature."
Date: November 15, 1960
Creator: Yavorsky, P. M. & Gorin, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Utilization of Radiactive Isotpoes in Coal Process Research

Description: "This is the first quarterly report on Task II of the subject Utilization of Radioactive Isotopes in Coal Process Research. There were two separate projects on Tank I; I. methods Development for Tritium Labeling of Coal Product Hydro-carbons, and II. Applications of Radio-Tracer Techniques to the Study of Fluidized Particle Mechanics. The following extended work on Task II concerns only Methods Development of Radio-Tracing With Tritium."
Date: August 15, 1960
Creator: Yavorsky, P. M. & Gorin, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The p-n Cross Sections onf Ti47, V51, Cr52, Co59, and Cu63 from 4 to 6.5 Mov

Description: Absolute (p,n) cross sections have been measured for Ti47, V51, Cr52, Co59, and Cu63 at energies between 4 and 6.5 Mov. These data plus earlier measurements of the cross section for inelastic proton scattering have been used to estimate total proton absorption cross sections for V51 and Co59. An optical model calculation using parameters giving a good fit to elastic scattering measurements predicts an absorption cross section in good agreement with the measurements for Co59. For V51, some sets … more
Date: June 15, 1960
Creator: Taketanit, H. & Alford, W. P. (William Parker), 1927-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thorium Oxide Infiltration of Graphite Spheres

Description: Work on the preparation of graphite spheres containing thorium oxide for use as breeder elements in the Pebble Bed Reactor-Steam Power Plant is described. Graphite spheres of varying density were infiltrated with thorium nitrate solutions, followed by denitration to thorium oxide.
Date: June 15, 1960
Creator: Parker, W. E. & Rusinko, F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Second Quarterly Report - The Study of the Potential Applications of Radioisotope Technology to Water Resource Investigations and Utiiization

Description: The objective of the study which is being carried out under contract AT(30-1)-2477 is the exploration of all aspects of research in water resources and supply to determine the potential for using radioisotope technology in this research. Problem areas in the application of tracers in this research are being investigated through the evaluation of past experimentation with radioisotopic techniques and through discussions with those who are active in this work. A series of suggestions relating to… more
Date: September 15, 1960
Creator: Isotopes Incorporated
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Computer description APPR-1 simulator

Description: The APPR-1 is a pressurized water reactor having a low specific heat fuel and a water primary coolant. The primary coolant loop delivers heat from the reactor to the steam generator. The secondary water in the steam generator is converted to steam and then taken to the turbine to drive an electrical generator. The simulation of this system is broken down into three primary areas: the neutron kinetics in the reactor which are necessary to generate the primary power function, the heat transfer… more
Date: December 15, 1958
Creator: RCA Service Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Charge on Uranium(VI) in Acid Solution

Description: Abstract. The distribution coefficient of U(VI) between perchloric acid solutions and benzene solutions of TTA has been measured as a function of the acidity. It was possible to interpret the data in terms of the charge on the U(VI) species present in the aqueous phase. The experiments indicate that U(VI) exists as an ion charge +2 at acidities from 0.1M to 2.5M. In the interpretations of the distribution data, it was necessary to know the acidity coefficient of the uranyl chelate in the ben… more
Date: August 15, 1946
Creator: King, Edward L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of Heavy Water by Equilibration

Description: Technical report discussing that the deuterium concentration of heavy water can be determined by equilibrating the water with deuterium gas in the presence of a catalyst with subsequent analysis of the equilibrated gas on the mas spectrometer. The apparatus for equilibration analyses maybe be considered in three parts: 1) apparatus for introducing the ingredients into the reaction chambers; 2) the reaction chambers; 3) the mass spectrometer for analysis of the equilibrated gas. The isotopic co… more
Date: May 15, 1945
Creator: Fischer, R. B.; Potter, R. A. & Voskuyl, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Crystal Structures of Some Uranium Compounds : a Summary from the Ames Laboratory

Description: Introduction. Some forty different uranium compounds have now been given diffraction study at Ames. Reports of these investigations are scattered in the Project literature; many have been reported in a sentence or two as a note along with chemical or metallographic reports. To make the results of this crystal structure work more available this summary of the Ames work has been compiled. (A similar summary has already been published from the Chicago laboratory.)
Date: August 15, 1945
Creator: Rundle, R. E.; Baenziger, N. C. & Wilson, A. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Month Ending March 15, 1945

Description: Technical report with short reports on (1) Effect of radiation on water and aqueous systems; (2) Gas evolution from uranyl solutions; (3) Effect of radiation on solid compounds; (4) Instruments; and (5) Scattering.
Date: March 15, 1945
Creator: Burton, Milton, 1902- & Allen, A. O. (Augustine O.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Electrolytic Production of Uranium from Solutions of its Tribromide in Fused Salts

Description: Abstract. the electrodeposition of uranium metal, in the form of tree-like deposits, from molten strontium halide baths is described. Under the best conditions studied, approximately 40% recovery is attained. Freedom from side-reactions of the reduced uranium with anode products and/or refractory materials, and high cathode current densities appear to be essential to the success of the process. the refining of uranium under similar conditions appears to occur quite readily, with approximatel… more
Date: August 15, 1944
Creator: Webster, Richard A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Uranium Oxide Slurry Pumping Experiments

Description: Abstract: Experiments on colloid milling and pumping show that uranium trioxide, when carefully dehydrated, can be dispersed in water to form a relatively stable slurry, suitable for a homogeneous slurry pile. At temperatures considerably below those of anticipated pile operation particle size growth occurs attended by increase in settling rate and decrease in viscosity. Theses properties of the slurries may be strongly affected by impurities present as well as by special operating condition… more
Date: September 15, 1944
Creator: Brandt, R. & Dean, G. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Month Ending May 15, 1943

Description: Technical report that information has bee obtained on the effect of beta and gamma radiation on the electrical resistance of insulating materials The results are summarized. The recovery to original resistance values has been measured. In general, the initial rate is rapid for the first few hours; the rate then decreases sharply. Certain samples show evidence of complete recovery. Effects on mechanical properties of several plastics has also been studied. Data on gas evolution from severa… more
Date: May 15, 1943
Creator: Franck, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Proton Irradiation Effects in Thorium

Description: "Iodide-processed thorium foils were irradiated with 9-Mev protons at temperatures below -140 degrees C. the recover of electrical resistance upon annealing was studied in the range 0 degrees to 75 degrees where tempering curves showed rapid changes taking place. Determinations of the activation energy associated with this process were made and the mean value obtained was 1.22 ev. Correlations of this result have been made with those found previously for copper. From these comparisons, a tenta… more
Date: December 15, 1954
Creator: Meechan, Charles J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Improved Method for Numerically Solving Multi-Group Reactor Equations

Description: "A method for solving multi-group reactor equations which arise in the diffusion approximation is outlined. Considerable work has been done on this problem at KAPL and ORNL. Their approach is to replace the differential equations by difference equations. Complications arise in this method where more than one slowing down medium is present since the fluxes are discontinuous at the interfaces. The primary purpose of this article is to develop an exact integral expression for the neutron flux w… more
Date: September 15, 1954
Creator: Lehman, G. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Distribution of Tracer Plutonium and Fission Products Between Molten Uranium and Solid Uranium Oxide, Carbide, and Nitride

Description: "A study has been made of the distribution of tracer fission products and plutonium between small samples of molten uranium and solid uranium oxide, carbine, and nitride. The distribution showed the same behavior i general for all three materials: 1. The rare earth elements, Cs, Ba, and Sr were extracted primarily into the solid scrub phase. 2. Zirconium and Nb partially concentrated in the scrub phase. 3. Plutonium, Mo, and Ru tended to remain completely in the metal phase. The distribution… more
Date: September 15, 1954
Creator: Keneshea, F. J.; Saul, A. M. & Young, C. Y.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Sodium Cooled, Graphite Moderated, Low Enrichment Uranium Reactor for the Production of Useful Power

Description: "A design study is presented for a sodium cooked, graphite moderated power reactor utilizing low enrichment uranium fuel. The design is characterized by dependence on existing technology and the use of standard, or nearly standard, components. The reactor has a nominal rating of 167 thermal megawatts, and a plant comprising three such reactors for a total output of 500 thermal megawatts is described. Sodium in a secondary, non-radioactive, circulation system carries the heat to a steam genera… more
Date: September 15, 1954
Creator: Weisner, Edward F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Heat Generation in Thermal Shields

Description: "Heat production resulting from the absorption of gamma ray photons in thermal shields and the leakage of neutrons and photons from ferritic thermal shields are investigated. The gamma rays considered arise from three types of reactor radiation -- thermal neutrons, fast neutrons, and core and reflector gammas. The energy spectra of the fast neutron leakage and absorption have been investigated in some detail because of the significant contribution of fast neutrons to the heating of the concre… more
Date: August 15, 1954
Creator: Heisler, M. & Wetch, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Development, Quarterly Progress Report, October-December 1953.

Description: Introduction - The work of the Chemical Development Group has included studies on the thermal and radiation stability of organic materials suitable for reactor coolants, the thermal and radiation stability of zirconium hydride, reactor safety devices involving chemical systems, and general analytical development.
Date: June 15, 1954
Creator: Loftness, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Uranium Production Reactor (UPR) Quarterly Progress Report, May-July, 1953

Description: "Measurements of the intra-cell neutron flux distributing for a proposed Uranium Production Reactor have been made using a mock-up of a portion of the reactor core. Thermal neutron and thorium resonance neutron flux-distributions were investigated. As a result of the experimental measurements on the first mock-up, a decrease in thorium content appeared necessary in the reactor design studies. Experiments are now in progress on a second mock-up in which this change has been made."
Date: March 15, 1954
Creator: Laubenstein, R. A.; Houghton, W. J. & Martin, D. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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