473 Matching Results

Search Results

Results: 1 - 24 next
open access

Fast Neutron Sensitivity of the CP Meter

Description: Abstract: "The sensitivity to fast neutrons of a CP Meter ionization chamber of the type used for health physics beta and gamma survey measurements has been investigated."
Date: June 10, 1949
Creator: Baker, E. E.; Gydesen, F. R. & Whipple, G. H., Jr.
Partner: UNT Libraries Government Documents Department
open access

The Solubility of Oxygen in Uranyl Sulphate Solutions at Elevated Temperatures

Description: Abstract: "The solubility of oxygen in uranyl sulphate solutions and in water at 212, 275, and 325 F, and at oxygen partial pressures up to 1500 psia was investigated. The results are presented in tabular and graphic form. The solubility is proportional to the partial pressure of oxygen. The ratio of solubility in the uranyl sulphate solution to solubility in water at the same temperature and pressure is a function of the concentration of the salt in solution."
Date: June 10, 1953
Creator: Pray, H. A. & Stephan, Elmer F.
Partner: UNT Libraries Government Documents Department
open access

Apparent viscosity of simulated underground metal waste slurries

Description: From introduction: "This report presents the apparent viscosities of supernate-sludge slurries prepared synthetically to simulate the conditions known to exist in the waste storage tanks, but with fission products and plutonium absent."
Date: June 20, 1950
Creator: Allen, A. W.
Partner: UNT Libraries Government Documents Department
open access

Ceramic Investigations of UOâ‚‚

Description: This report covers the progress made on an intensive program to develop and evaluate UO2 as a possible fuel element for the PWR.
Date: June 16, 1955
Creator: Allison, Adrian G. & Duckworth, Winston H.
Partner: UNT Libraries Government Documents Department
open access

General Engineering and Consulting Laboratory "Hot Service" Turbine Pump Progress Report: May 1 to June 15, 1948

Description: Introduction: "This report covers progress on the testing of the General Engineering and Consulting Laboratories Turbine Pump No. 1 from May 1, 1948 to Jun 15, 1948. All testing prior to April 30, 1948 has been described in Redox Experiment Testing Report No. 1 (Document HW-9474) and No. 2 (Document HW-9694)."
Date: June 21, 1948
Creator: Stringer, J. T. & Allen, A. W.
Partner: UNT Libraries Government Documents Department
open access

Zirconium Pheylarsonate Tracer Scale Method for the Differentiation of Pu(III) and Pu(IV) in Redox Solutions

Description: The following report studies an estimation of the amount of Pu(III) and Pu(IV) present in the IBP Stream, with the purpose of establishing an analytical, method suitable for routine control analysis. A method is discussed that is based on carrying Pu(IV) upon a zirconium phanylarsonate precipitate.
Date: June 30, 1948
Creator: Ice, C. H.
Partner: UNT Libraries Government Documents Department
open access

The Boron-Carbon System: Final Technical Report, May 1, 1960 - April 30, 1961

Description: Abstract: The boron-carbon equilibrium diagram has been determined by X-ray, metallographic, and thermal analysis of sintered and arc-cast alloys. A single carbide having a range of solubility from approximately 9 to 20 a/o carbon and melting congruently exists in the system. The terminal solubility of carbon in boron is 0.1-0.2a/o. The freezing reaction at the composition and melting temperature of elemental boron; there is a eutectic reaction at 29a/o carbon and 2375 degrees Celcius. No allot… more
Date: June 7, 1961
Creator: Elliott, Rodney P.
Partner: UNT Libraries Government Documents Department
open access

Investigation of Graphite Bodies : Progress Report No. 3 for the Period March 1, 1959 to May 31, 1959

Description: This document is the third in a series of progress report that records investigations of graphite bodies. Along with the report, two appendices are given to describe the different graphite bodies: "Synthetic Binders for Carbon and Graphite" and "High Temperature Physical Properties of Molded Graphites".
Date: June 10, 1959
Creator: Bradstreet, Samuel W.
Partner: UNT Libraries Government Documents Department
open access

Grain Refinement of Uranium by Alloying

Description: Binary alloys of uranium with 38 elements in the range 0.01 to 1.0 at.% were made. Three alloys having nominal compositions of 0.01, 0.1, and 1.0 at.% were made with most of the elements, and in addition, 12 ternary and quaternary alloys were made. The alloys were cast, rolled to 7/8-inch-diameter bars, heat treated, and examined for grain size.
Date: June 1, 1951
Creator: Saller, Henry A.; Keeler, J. R. & Eddy, N. S.
Partner: UNT Libraries Government Documents Department
open access

Jacketing of Uranium for High-Temperture Service

Description: From introduction: "The work covered in this report is a portion of the experimental research undertaken for the design of a uranium-containing metallic fuel rod for operation in air at 1090 C...This report deals with that phase which involved the testing and evaluation of various metals as barrier costs between uranium alloys, and low-carbon steel. The work is of a preliminary nature and is concerned more with a comparison of the various barrier metals than with the acquisition of numerical da… more
Date: June 1, 1951
Creator: Saller, Henry A. & Stacy, J. T.
Partner: UNT Libraries Government Documents Department
open access

Quarterly Progress Report on Refining of MgX and Other Uranium-Bearing Materials

Description: From abstract: "Results are presented of Scheibel column extraction tests with neutral ether on a variety of combinations of feed solutions...The effect of added iron was evaluated for a considerable number of process solutions and slurries. Arsenic was traced through both primary and secondary extraction stages in one test."
Date: June 30, 1951
Creator: Ewing, R. A.; Kiehl, S. J., Jr.; Bearse, A. E. & Sharpe, R. E.
Partner: UNT Libraries Government Documents Department
open access

The Ammonium Carbonate Pressure Leaching of Uranium Ores Proposed as Feed to the Pilot Plant at Grand Junction, Colorado : Progress Report

Description: From introduction: This is Progress report BMI-282, the first of a series covering the operation of the pressure-leaching towers for the extraction of uranium by an ammonium carbonate leach...This report discusses the data obtained from tests run to show the effects of such variables as the amount of air and carbon dioxide passed through the pulp, temperature, pressure, and concentration of ammonium carbonate and ammonium bicarbonate in the leach solution on the extraction of uranium.
Date: June 15, 1955
Creator: Wheeler, C. M.; Langston, B. G. & Stephens, F. M., Jr.
Partner: UNT Libraries Government Documents Department
open access

Determination of Rare Earths in Refined Uranium : Topical Report

Description: Abstract: "Rare-earth analyses were performed on several samples of refined uranium oxide and nitrate, using a modified cellulose column procedure. Rare earths were not detectable in samples of 0.03 shotgun of less. Detection limits were from 0.0005 to 0.015 ppm. Negligible quantities of low-cross-section rare earths were found in less pure uranium samples, obtained during start-up operations of the pilot plant at the Feed Materials Production Center, primarily those rare earths of greater than… more
Date: June 30, 1953
Creator: Ewing, R. A. & Bearse, A. E.
Partner: UNT Libraries Government Documents Department
open access

Alloys of Uranium with Zirconium, Chromium, Columbium, Vanadium, and Molybdenum

Description: Abstract: Information on five uranium binary alloy systems has been surveyed. These systems are the alloys of uranium with zirconium, chromium, columbium, vanadium, and molybdenum. The equilibrium diagrams are discussed, and where available, data have been included on diffusion studies, cladding experiments, and mechanical properties.
Date: June 19, 1952
Creator: Saller, Henry A. & Rough, Frank A.
Partner: UNT Libraries Government Documents Department
open access

Corrosion-Resistant Materials for Hydrofluoric Acid : Progress Report

Description: Introduction: Among the many corrosion problems encountered in the production of uranium tetrafluoride and uranium metal from ores and concentrates, some of the most serious occur where hydrofluoric acid must be handled.
Date: June 15, 1953
Creator: Pray, H. A.; Fink, F. W.; Friedl, B. E. & Braun, W. J.
Partner: UNT Libraries Government Documents Department
open access

Progress Report on the Concentration of Pitchblende

Description: Abstract: "Additional work on the flotation of sulphides from high-sulphur pitchblende is described. Data needed for the selection of flotation equipment are presented."
Date: June 30, 1950
Creator: Wesner, A. L.; Tangel, O. F. & Richardson, A. C.
Partner: UNT Libraries Government Documents Department
open access

Feasibility Study of a New Mass Flow System : Quarterly Report No. 4 Covering the Period from March 1, 1961 to May 31, 1961

Description: This is the fourth quarterly report that documents a system of mass flow that can record measurements of homogeneous flow, slurries, highly corrosive fluids and multiphase fluids, additionally considering pressure drops, measuring external to the flow, ruggedness and reliability.
Date: June 23, 1961
Creator: Haffner, J. W.; Stone, C. A. & Genthe, William K.
Partner: UNT Libraries Government Documents Department
open access

Bibliography : Impact Testing of Materials

Description: The bibliography provided investigates the following sources: Chemical Abstracts 1947-1950., Metallurgical Abstracts Vols. 1-18., ASM Review of Metals Literature Vols. 1-6., J. Institute of Metals Vols. 78-80 (No. 7)., Physics Abstracts 1937-1950.
Date: June 8, 1952
Creator: Fick, Jean
Partner: UNT Libraries Government Documents Department
open access

Radiation Shielding for Test Cell "C"

Description: "This report contains information on the following topics related to the radiation shielding at test cell "C". (1) Calculation of wall and roof thicknesses. (2) Calculation of radiation heating of front wall by gamma and neutron absorption. (3) Calculation of neutron activation in front face of test cell. (4) Calculation of γ-dose rates both direct and behind shadow shields at various distances. (5) Dose produced by a reactor catastrophe."
Date: June 1959
Creator: Fenstermacher, Charles Alvin & Henshall, James
Partner: UNT Libraries Government Documents Department
open access

Nondestructive Measurements of Aluminum and Nickel Layers on Uranium

Description: From introduction: "This report covers the development of nondestructive techniques for measuring quantitatively: (1) thickness of electrodeposited-nickel diffusion barriers, and (2) thickness of aluminum cladding on flat-plate fuel elements."
Date: June 12, 1954
Creator: Glaze, E. W.; Rhoten, M. L.; Kulp, B. A.; Cooley, K. D. & Wenk, S. A.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen