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.
Object Type: Report
System: The UNT Digital Library
The Solubility of Oxygen in Uranyl Sulphate Solutions at Elevated Temperatures (open access)

The Solubility of Oxygen in Uranyl Sulphate Solutions at Elevated Temperatures

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.
Object Type: Report
System: The UNT Digital Library
Apparent viscosity of simulated underground metal waste slurries (open access)

Apparent viscosity of simulated underground metal waste slurries

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.
Object Type: Report
System: The UNT Digital Library
Ceramic Investigations of UO₂ (open access)

Ceramic Investigations of UO₂

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.
Object Type: Report
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.
Object Type: Report
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.
Object Type: Report
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.
Object Type: Report
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.
Object Type: Report
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.
Object Type: Report
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
Object Type: Report
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.
Object Type: Report
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.
Object Type: Report
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.
Object Type: Report
System: The UNT Digital Library
Quarterly Progress Report on Refining of MgX and Other Uranium-Bearing Materials (open access)

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

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.
Object Type: Report
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.
Object Type: Report
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.
Object Type: Report
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.
Object Type: Report
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.
Object Type: Report
System: The UNT Digital Library
Progress Report on the Concentration of Pitchblende (open access)

Progress Report on the Concentration of Pitchblende

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.
Object Type: Report
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.
Object Type: Report
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.
Object Type: Report
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
Object Type: Report
System: The UNT Digital Library
Radiation Shielding for Test Cell "C" (open access)

Radiation Shielding for Test Cell "C"

"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
Object Type: Report
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.
Object Type: Report
System: The UNT Digital Library