UNT Libraries Government Documents Department - 5,422 Matching Results

Search Results

open access

IBM Multigroup Numerical Procedures

Description: Introduction: "This paper presents in formula form IBM computational procedure for averaging cross-section data and for calculating reflected spherical reactors by the linear by the linear multigroup numerical method developed by the Physics Section of the ANP Central Design Group. The adjoint reactor numerical procedural is included."
Date: November 28, 1950
Creator: Holmes, David K. & Schulze, O. A.
open access

The Preparation and Some Properties of a Uranium Hexafluoride-Sodium Fluoride Complex

Description: Report discussing "preparation of some stable complexes of uranium hexafluoride with sodium, potassium, and thallium fluorides...Such compounds, reported as stable in air and of low vapor pressure, offered promise as convenient sources of unoxygenated hexa-valent uranium without the difficulties associated with the use of uranium hexafluoride itself."
Date: November 30, 1950
Creator: Horton, Charles A.; Harris, Warren W.; Barr, John T. & Posey, J. C.
open access

Isotopes of Neptunium and Plutonium

Description: This report describes work done that originated in an effort to identify previously unknown isotopes of neptunium and plutonium and to characterize a few that were known for extension of the nuclear energy surface. The findings of this work results in two new light plutonium isotopes and one heavy neptunium isotope that were produced by bombardment of uranium with helium and deuteron ions from a 60-inch cyclotron and a 184-inch cyclotron. The chemical and experimental methods are described as w… more
Date: December 1950
Creator: Orth, Donald Alfred
open access

The Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending August 31, 1950

Description: Technical report outlining various experiments that took place in the Oak Ridge Area Critical Mass Laboratory until August 31, 1950. Experiments took place in categories of critical experiments, experimental engineering, heat transfer, radiation damage, nuclear measurements, reactor physics, ARE reactor design, circulating fuel reactors, and circulating moderator reactors. [From Summary]
Date: December 4, 1950
Creator: Ellis, C. B. & Thompson, W. E.
open access

A Preliminary Survey of Radioactive Constituents in Rainwater at ORNL

Description: Technical report surveying radio-chemical analyses by ORNL's Analytical Chemistry Division and Health-Physics Division of large volumes of rainwater for plutonium, uranium, and fission products. Overall, carrying efficiencies for Al(OH)3 scavenging of rainwater were determined for these elements, as well as for Pu and U. [From Abstract, Introduction]
Date: December 4, 1950
Creator: Booksbank, W. A., Jr.; Emmons, A. H.; Gost, J. W. & Reynolds, S. A.
open access

Evaluation of Tributyl Phosphate in Jet Mixing Columns as a Solvent for Uranium Extraction From Slurry-Type Ore Feeds

Description: Technical report outlining the physical operability of 30% tributyl phosphate in a hydrocarbon dilutent for the extraction of uranium from more feed slurries. Operability had been satisfactorily demonstrated in jet mixing columns at the pilot plant of the Mallinckrodt Chemical Works. [From Abstract]
Date: December 7, 1950
Creator: Runion, T. C. & Yeager, J. H.
open access

The Determination of Indium in Indium Plutonium Solutions

Description: Abstract: "A gravimetric procedure is described for the analysis of indium-plutonium solutions. This procedure consists of a preliminary separation of the plutonium as the peroxide, followed by the quantitative precipitation of indium diethyl dithio carbamate from a slightly acid solution. The precipitate is dried at 105 C and weighed. Recoveries of 99.4 - 100.5% with an average precision of 2.3/100 were obtained on known Pu-In solutions containing 5 - 50 mg of indium per sample."
Date: December 12, 1950
Creator: Waterbury, Glenn R.
open access

Measurements of an Iron and Borated Water Shield in the Lid Tank : Experiment 10

Description: The following report measures a shield mockup in three regions: the first made almost entire of iron; the second, transition, region is made of various thicknesses of B4C; and the third region was borated water. The iron samples used in the experiments were made in the form of rectangular plates and place in the lid tank; however, the plates were not completely flat and created a water gap that was measured in this report.
Date: December 14, 1950
Creator: Blizard, E. P. & Clifford, C. E.
open access

Research on Reactor Waste Disposal: (Information Report)

Description: Report discussing research on the disposal of radioactive waste, specifically second-cycle waste and first-cycle neutralized waste. "In the absence of established environmental tolerances, the investigation reported herein have been directed for the most part in developing general methods of removing radioactivity from certain waste solutions to as low a value as practical."
Date: December 15, 1950
Creator: Lowe, C. S.; McEwen, M.; Mead, F. C., Jr. & Orban, Edward
open access

The Corrosion of Miniature Fuel Plates in Simulated Reactor Cooling Water

Description: Technical report issued as one of a series of reports concerned with corrosion studies for the Materials Resting Reactor, created to both determine the effect of various practices for fuel plate fabrication on corrosion resistance and to determine the extent of penetration of the fuel plates by localized corrosion attack. [From Introduction]
Date: December 18, 1950
Creator: English, James L.
open access

Angular distribution of neutrons from a plane surface

Description: From introduction: "This report determines lattice losses by considering the angular distribution of the neutrons emitted from the interior faces of the lattice and the exterior faces of the target. The purpose of this report is to investigate this problem by considering the dimensions of the faces to be large compared to the total mean free path."
Date: 1951
Creator: Harker, Wesley H.
open access

Annie Laurie Prospect, Santa Cruz County, Arizona

Description: From introduction: The Annie Laurie 'cranium Prospect, in the Oro Blanco district of southern Arizona, is located in the southwest quarter of Sect. 3, T233, R=13. The nearest United States post office is Nogales, about 25 miles east, and the nearest settlement is Ruby, a nearly abandoned mining camp about 3 miles north. Access to the Ruby area is by gravel road from US highway 39 at Kinsley or Nogales. The Ruby quadrangle (1940) includes the area surrounding the prospect.
Date: January 1951
Creator: Wright, Robert J.
open access

Calculated thermal conductivities of pure gases and gaseous mixtures at elevated temperatures

Description: From summary: "A method of calculating thermal conductivities of gases and mixtures of gases at elevated temperatures is presented. Results for carbon dioxide, helium, neon, nitrogen, and their binary mixtures are given for the temperature range of 273 degrees Kelvin to 800 degrees Kelvin. The calculated results for the pure gases are in agreement with the known experimental data."
Date: 1951
Creator: Wright, J. M.
open access

The Chelate Process, IV. Process Flow Involving o-Dichlorobenzene as the Solvent for TTA

Description: Comparative studies of a series of halogenated solvents, as carriers for TTA in the chelate process for plutonium extraction, indicate that ortho-dichlorobenzene most nearly satisfies the requirements that are set forth. A complete process design is presented for use with this solvent, and flow data and equipment capacities are given for dissolver solution and for uranium-free fission product solution as alternate feeds to the process.
Date: January 1951
Creator: Davis, M. W., Jr.; Hicks, T. E. & Vermeulen, T.
open access

The Determination of Zirconium

Description: Abstract: "The method of Hayes and Jones, which uses p-dimethylaminoasophenylarsonic acid to precipitate zirconium, was studied for the range of one to seven micrograms of zirconium. The most strongly interfering ions, namely phosphate, fluoride, sulfate and the tetravalent cations of uranium, thorium and plutonium were studied. Two procedures are suggested."
Date: 1951
Creator: Stehney, A. F. & Safranski, L. W.
open access

The Development and Application of Capillary Absorption Cells

Description: Abstract: "Various types of capillary absorption cells have been constructed from a variety of materials. These cells, having volumes as low as 160 microliters, have been used to increase the sensitivity of several colorimetrics methods as much as 1000 fold without appreciable loss of accuracy. Small volumes of solution must be used in order to concentrate the colored material present."
Date: 1951
Creator: Rosenfels, R. S.; Kirk, P. L.; Kitson, R. E.; Patton, R. L. & Curtis, R. E.
Back to Top of Screen