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Hydrogeochemical and Stream Sediment Reconnaissance Basic Data Lund Quadrangle, Nevada and Utah

Description: "Field and laboratory data are presented for 1795 sediment samples from the Lund Quadrangle, Nevada; Utah. The samples were collected by the Savannah River Laboratory; laboratory analysis and data reporting were performed by the Uranium Resource Evaluation Project at oak ridge, Tennessee." (from Abstract)
Date: October 1, 1981
Creator: National Uranium Resource Evaluation Program
Location: None
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Hydrogeochemical and Stream Sediment Reconnaissance Basic Data Bakersfield Quadrangle, California

Description: "Field and laboratory data are presented for 1780 sediment samples from the Bakersfield Quadrangle, California. The samples were collected by the Savannah River Laboratory; laboratory analysis and data reporting were performed by the uranium resource Evaluation Project at Oak Ridge Tennessee." (from Abstract)
Date: October 1, 1981
Creator: National Uranium Resource Evaluation Program
Location: None
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Hydrogeochemical and Stream Sediment Reconnaissance Basic Data Goldfield Quadrangle, California and Nevada

Description: "Field and laboratory data are presented for 790 sediment samples from the Goldfield Quadrangle, California; Nevada. The samples were collected by savannah River Laboratory; laboratory analysis and data reporting were performed by the Uranium Resource evaluation Project at Oak Ridge, Tennessee." (from Abstract)
Date: October 1, 1981
Creator: National Uranium Resource Evaluation Program
Location: None
open access

Hydrogeochemical and Stream Sediment Reconnaissance Basic Data for San Luis Obispo Quadrangle, California

Description: "Feild and laboratory data are presented for 665 sediment samples from the San Luis Obispo Quadrangle, California. The samples were collected by the Savannah River Laboratory; laboratory analysis and data reporting were performed by the Uranium Resource Evaluation Project at Oak Ridge, Tennessee."
Date: October 1, 1981
Creator: National Uranium Resource Evaluation Program
Location: None
open access

Test Results on Clinton Alpha Amplifier Used with an Offner Columbia Scaler

Description: Technical report describing development of the Clinton alpha amplifier. The circuit for the Clinton alpha amplifier which is used with an Offner scaler is shown attached to the report. It consists of a pre-amplifier mounted in a cylindrical alpha chamber, followed by a three state amplifier and a pulse height selector in a separate cabinet. Pulses are fed from the pulse height selector in the amplifier to the input tube of the Offner scaler. Through the third stage of the amplifier, this circuit is exactly the same as the California circuit now used by the chemical section for alpha counting. A type 961 Offner scaler was used for these tests. None of the latest Offner scalers type961A, were available to us when the tests were made. Method of testing is given, results are tabulated, computations are made, and eight graphs are given. it appears that the Clinton amplifiers used with a Offner scaler will give substantially the same performance as that given by the California circuit.
Date: July 1, 1944
Creator: Ostdahl, H. E.
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High Frequency Induction Heating

Description: Abstract: Equations are given to calculate at least approximately the heating in solid and hollow cylinders, slabs and spheres. Short and long cylinders are treated as well as short and long solenoids. The complicated mathematics used to derive the equations given will be omitted as they may be found in the original references. Heating with a spark gap converter is covered. Equations are given which together with some experimental data should enable the reader to predict the efficiency, heating, or temperature to be expected as the charge or coil is changed. Units and conversion factors are mentioned briefly.
Date: February 1, 1947
Creator: Bromley, LeRoy A.
open access

The Use and Calibration of Scintillation Counter--Model Y

Description: Several improvements have been made in the gamma scintillation counter (GSC). The Model V gamma scintillation counter uses a canned thallium activated sodium iodide crystal as a detector. Although the electronic components remain unchanged, a modification of the sample support has been made to improve reproducibility of geometry. To assure comparable results between various counters, they must be operated at the same energy threshold and counting yield. Methods have been developed to assure operation at a preferred energy threshold of 0.1 Mev and an arbitrarily fixed counting yield of 3.36% for Cs-Ba-137. Partial pulse height discrimination against U 237 is also accomplished.
Date: August 1, 1953
Creator: Brauer, F. P. & Leboeuf, M. B.
open access

Physical Properties of Tributylphosphate-Diluent Solutions

Description: In connection with the study of aqueous-tributyIphosphate (TBP) systems, the study of the interactions of various diluents with the TBP has been extended. The diluents used were mineral oil, Amsco 125-90W, dodecane, n-hexane, cyclohexane, benzene, n-octyl bromide, carbon tetrachloride, chloroform and pentachloroethane. The solubility of TBP in water from solutions of these diluents and the solubility of water in the organic phase was determined. For the paraffin hydrocarbons as diluents the solubility of TBP in water was found to increase with increasing molal volume of the diluent. No evidence for the formation of TBP-water complex of simple mole ration was found.
Date: September 1, 1953
Creator: Johnson, W. F. & Dillon, R. L.
open access

The Ratio of Plutonium 239 to Uranium 235 Fission Cross Sections from 0.020 to 1.0 Electron Volts

Description: Foils of plutonium 239 and uranium 235 have been mounted back to back in a dual ionization fission chamber in the diffracted beam of the Hanford neutron crystal spectrometer. A quantity proportional to the ration of fission cross sections of Pu239 to U235 has been measured as a function of neutron energy from 0.020 to 1.0 electron volts. The results of this investigation are presented graphically in the text.
Date: December 1, 1953
Creator: Leonard, B. R., Jr.; Hauser, S. M. & Seppi, E. J.
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Relative Effectiveness of Various Agents for Preventing the Internal Deposition of Plutonium in the Rat

Description: The prompt administration of zirconium citrate was at least twice as effective as the prompt administration of calcium disodium salt of ethylenediaminetetraacetic acid (CaEDTA) in preventing deposition of plutonium in the skeleton. On the other hand, CaEDTA was twice as effective as zirconium citrate in preventing the deposition of plutonium in soft tissues. The combined administration of zirconium citrate and CaEDTA was the most effective treatment for preventing the deposition of plutonium in the total rat. Zirconium malate offered no advantage over zirconium citrate, and appeared to be somewhat more toxic. Three doses of the zirconium salts over a four-day period were no more effective than a single dose.
Date: January 1, 1954
Creator: Katz, J.; Weeks, M. H. & Oakley, W. D.
open access

The Chelate Process III : Preliminary Continuous-Operation Studies

Description: Abstract: The rate of extraction of PuIV in either direction between benzene-TTA and aqueous HNO3 solutions is shown in the present study to be fast enough so that application of the chelate process to continuous operation should be feasible. This conclusion is based on two primary considerations: 1. The mechanism limiting the rate of extraction appears to be diffusion and not chemical-reaction-limiting. 2. The extraction may be controlled by adjustment of the system conditions to give almost any desired specifications of rate and/or equilibrium. A continuous process involving multiple extraction stages with a controlled pH gradient is proposed for obtaining maximum decontamination and plutonium recovery.
Date: June 1, 1948
Creator: Rubin, B. (Barney), 1924- & Hicks, T. E.
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