Language

Fast Neutron Sensitivity of the CP Meter (open access)

Fast Neutron Sensitivity of the CP Meter

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.
System: The UNT Digital Library
Ceramic Investigations of UOâ‚‚ (open access)

Ceramic Investigations of UOâ‚‚

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.
System: The UNT Digital Library
General Engineering and Consulting Laboratory "Hot Service" Turbine Pump Progress Report: May 1 to June 15, 1948 (open access)

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

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.
System: The UNT Digital Library
Zirconium Pheylarsonate Tracer Scale Method for the Differentiation of Pu(III) and Pu(IV) in Redox Solutions (open access)

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

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.
System: The UNT Digital Library
Delayed Failure Hydrogen Embrittlement of Zirconium: Quarterly Report Number 3, March - June 1962 (open access)

Delayed Failure Hydrogen Embrittlement of Zirconium: Quarterly Report Number 3, March - June 1962

The following report is the third Quarterly Report in a series whose investigative purpose is to determine the extent to which zirconium and zirconium alloys exhibit delayed failure as caused by a combination of absorbed hydrogen and applied stress.
Date: June 6, 1962
Creator: Weinstein, Daniel & Holtz, F. C.
System: The UNT Digital Library
Magnetic Properties of Insulators : Quarterly Report No. 9 Covering the Period from February 16, 1963 to May 15, 1963 (open access)

Magnetic Properties of Insulators : Quarterly Report No. 9 Covering the Period from February 16, 1963 to May 15, 1963

The following quarterly report covers the period during February 16 to May 15, 1963. This report is divided into sections covering the separate activities during this period, studying the thermal behavior of the F-center in RbCl.
Date: June 5, 1963
Creator: Markham, Jordan J.
System: The UNT Digital Library
The Boron-Carbon System: Final Technical Report, May 1, 1960 - April 30, 1961 (open access)

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

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 allotropy of boron was observed.
Date: June 7, 1961
Creator: Elliott, Rodney P.
System: The UNT Digital Library
Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Seventh Letter Report, April 1 to May 31, 1959 (open access)

Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Seventh Letter Report, April 1 to May 31, 1959

Introduction: "This is the seventh letter report on ARF Project C 127, entitled "Preliminary Studies of Scavenging Systems Related to Radioactive Fallout." This report covers the period from April 1 to May 31, 1959."
Date: June 15, 1959
Creator: Stockham, John D. & Rosinski, John
System: The UNT Digital Library
Investigation of Graphite Bodies : Progress Report No. 3 for the Period March 1, 1959 to May 31, 1959 (open access)

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

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.
System: The UNT Digital Library
Grain Refinement of Uranium by Alloying (open access)

Grain Refinement of Uranium by Alloying

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.
System: The UNT Digital Library
Jacketing of Uranium for High-Temperture Service (open access)

Jacketing of Uranium for High-Temperture Service

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 data, e.g., diffusion coefficients."
Date: June 1, 1951
Creator: Saller, Henry A. & Stacy, J. T.
System: The UNT Digital Library
The Ammonium Carbonate Pressure Leaching of Uranium Ores Proposed as Feed to the Pilot Plant at Grand Junction, Colorado : Progress Report (open access)

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

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.
System: The UNT Digital Library
Determination of Rare Earths in Refined Uranium : Topical Report (open access)

Determination of Rare Earths in Refined Uranium : Topical Report

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 average abundance in nature. No correlation was found between rare-earth content and shotgun values. Rare earths do not appear to be contributing significantly to the neutron absorption of refined uranium. A modified cellulose column procedure, which includes a preconcentration solvent-extraction step, is described. Radioactive tracer tests indicating rare-earth recoveries by the method of >98 per cent are reported."
Date: June 30, 1953
Creator: Ewing, R. A. & Bearse, A. E.
System: The UNT Digital Library
Alloys of Uranium with Zirconium, Chromium, Columbium, Vanadium, and Molybdenum (open access)

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

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.
System: The UNT Digital Library
Corrosion-Resistant Materials for Hydrofluoric Acid : Progress Report (open access)

Corrosion-Resistant Materials for Hydrofluoric Acid : Progress Report

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

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.
System: The UNT Digital Library
Development and Evaluation of High-Temperature Tungsten Alloys: Quarterly Report Number 2, January - March 1960 (open access)

Development and Evaluation of High-Temperature Tungsten Alloys: Quarterly Report Number 2, January - March 1960

Quarterly report describing progress on a project to develop and evaluate high-temperature tungsten alloys. This report discusses properties for specific base alloys at room temperature and under high temperatures.
Date: June 24, 1960
Creator: Holtz, F. C. & Van Thyne, R. J.
System: The UNT Digital Library
Bibliography : Impact Testing of Materials (open access)

Bibliography : Impact Testing of Materials

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
System: The UNT Digital Library
Nondestructive Measurements of Aluminum and Nickel Layers on Uranium (open access)

Nondestructive Measurements of Aluminum and Nickel Layers on Uranium

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.
System: The UNT Digital Library
An Experimental Survey of the Heat-Treatment Response of some Zirconium-Uranium Alloys (open access)

An Experimental Survey of the Heat-Treatment Response of some Zirconium-Uranium Alloys

Abstract: "The heat-treatment behavior of zirconium alloys containing 7 to 70 w/o uranium is described. The effect of oxygen contamination on the structure and hardness of these alloys is outlined. It is shown that in the initial stages pf transformation of beta zirconium-uranium solid solution into the low-temperature phases a potent hardening reaction occurs in alloys containing 20 to 70 w/o uranium. In this reaction the hardness may rise from 200 DPH characteristic of retained beta to values in excess of 400 DPH. Practical heat treatments have been developed which produce relatively soft alloys. The microstructures and hardnesses produces by these treatments are shown."
Date: June 15, 1956
Creator: Saller, Henry A.; Rough, Frank A. & Chubb, Walston
System: The UNT Digital Library
Differential Thermal Analysis of Uranium Tetrafluoride-Uranium Dioxide Mixtures (open access)

Differential Thermal Analysis of Uranium Tetrafluoride-Uranium Dioxide Mixtures

Abstract: "Approximate melting points have been determined for five samples of uranium tetrafluoride representing incompletely converted uranium dioxide and covering the range from about 2 to 20 w/o UO2, using the method of differential thermal analysis. The results indicate the melting temperatures are in the range of 920 to 980 C. No significant correlation between melting point and UO2 content was observed, possibly because of calcite formation. Similar results were obtained on synthetic mistakes of UF4 containing from 10 to 40 w/o UO2."
Date: June 28, 1956
Creator: Ewing, Robert A. & Bearse, Arthur E.
System: The UNT Digital Library
An Improved Nuclear Density Gauge : Covering the Interval of June 1 to July 1, 1959 (open access)

An Improved Nuclear Density Gauge : Covering the Interval of June 1 to July 1, 1959

The following document is a note describing the building process of an improved nuclear density gauge in comparison to previous gauges, within the interval of June 1 to July 1, 1959.
Date: June 8, 1959
Creator: Burgwald, G. M. & Stone, C. A.
System: The UNT Digital Library
Determination of Organic Acids in Process Solutions (open access)

Determination of Organic Acids in Process Solutions

Abstract: "A method has been established for the estimation of volatile organic acids in aqueous process solutions containing UNH, nitric acid, ANN, sodium dichromate and small amounts of hexone. The practice is to distill a 400 ul or 500 ul sample in the presence of an excess of phosphoric acid and ferrous sulfate under a high vacuum; a special apparatus utilizing a receiver cooled with a dry ice-isopropanol mixture is employed. The distillate is taken up in isopropanol and then titrated potentiometrically with standard potassium hydroxide solution. Since nitric acid and organic acids are present, two end points are observed. The potassium hydroxide added between these end points is equivalent to the organic acids. In the titration, CO2 from the atmosphere or in the potassium hydroxide is a source of error. The former was avoided and correction was made for the latter."
Date: June 29, 1949
Creator: Brouns, R. J. & Pollock, C. W.
System: The UNT Digital Library
The Coulometric Titration of 8-Hydroxyquinoline (open access)

The Coulometric Titration of 8-Hydroxyquinoline

Abstract: "A new method of determining 8-hydroxyquinoline by titration with electrolytucally-generated bromine has been developed. Results show good precision in the range 0.4 mg. to 1.6 mg. total 8-hydroxyquinoline, with 99% confidence limits of less than +/- 2%. An electronically-regulated constant current source, required by the method, is described. A new indicator system with high sensitivity to free bromine is discussed."
Date: June 16, 1949
Creator: Carson, W. N.
System: The UNT Digital Library