Degree Level

Collection and Analysis of Active Particles (open access)

Collection and Analysis of Active Particles

Abstract: This report gives the results of a radiochemical analysis of particles collected by electrostatic precipitation from ventilation air of the "B" plant at Hanford Works.
Date: January 27, 1950
Creator: DeLong, C. W.
Object Type: Report
System: The UNT Digital Library
Corrosion of Construction Materials in 234-5 Project Solutions (open access)

Corrosion of Construction Materials in 234-5 Project Solutions

The following report covers the construction materials selected for laboratory corrosion studies and the determination of their corrosion rates in process solutions.
Date: January 31, 1950
Creator: Koenig, W. W.
Object Type: Report
System: The UNT Digital Library
A comparison of two methods for the spectrochemical analysis of plutonium (open access)

A comparison of two methods for the spectrochemical analysis of plutonium

Report describing the methods, discrepancies, accuracy of methods, and conclusions of two different analytical methods of spectrochemical analysis of plutionium.
Date: February 1, 1950
Creator: Van Tuyl, H. H.
Object Type: Report
System: The UNT Digital Library
The Determination of Total Plutonium in the Presence of Aluminum (open access)

The Determination of Total Plutonium in the Presence of Aluminum

Introduction: "The adoption of aluminum nitrate as salting agent in the Redox process made it imperative that a method be available for determining plutonium in the presence of aluminum. However, large amounts of aluminum have been found to interfere with the determination of plutonium by the lanthanum fluoride procedure. Previous attempts to increase the accuracy of the lanthanum fluoride method, by precipitating LaF3 from 4 M HF (rather than 2 M), have been successful only when the initial plutonium level was high."
Date: February 10, 1950
Creator: Burns, R. E. & Barton, G. B.
Object Type: Report
System: The UNT Digital Library
Chemical Research Section Progress Report for January 1950 (open access)

Chemical Research Section Progress Report for January 1950

The following documents are progress reports that follow chemical research studies in subjects such as ruthenium tetroxile distillations, extraction-scrub studies of zirconium and niobium, and oxidation of plutonium and stabilization of plutonium(VI) during extraction of IAF solutions.
Date: February 15, 1950
Creator: Albaugh, F. W.
Object Type: Report
System: The UNT Digital Library
Process Tube Temperature Mapping : Progress Report (open access)

Process Tube Temperature Mapping : Progress Report

This report discusses a method for scanning process tubes for temperature and displaying a reactor's temperatures for monitoring.
Date: 1950
Creator: Hoff, Rodney G.
Object Type: Report
System: The UNT Digital Library
Corrosion of Austenitic Stainless Steel Type 347 in Redox Process Stream : (ORNL #1 Flowsheet) (open access)

Corrosion of Austenitic Stainless Steel Type 347 in Redox Process Stream : (ORNL #1 Flowsheet)

The following report provides the results of laboratory corrosion tests held to investigate the behavior of austenitic stainless steel, Type 347, in selected O.R.N.L. #1 Redox streams.
Date: February 23, 1950
Creator: Koenig, W. W.
Object Type: Report
System: The UNT Digital Library
The Coulometric Determination of Acid (open access)

The Coulometric Determination of Acid

Introduction: "The need for a method of acid determination which could be used for small samples and easily adapted to remote control led to the investigation of the use of electrolytically generated base for the titration of acid in certain solutions. The use of electrolytically generated base for the titration of acetic acid in the presence of nitric acid has been reported (1)."
Date: March 1, 1950
Creator: Carson, W. N. & Ko, Roy
Object Type: Report
System: The UNT Digital Library
The Development of Plutonium Electrodeposition Methods : Interim Report (open access)

The Development of Plutonium Electrodeposition Methods : Interim Report

From introduction: "The following report presents a body of information obtained in the Health Instrument Development Laboratory from September, 1948, to the present, and is intended to be a preliminary review of [the study of electrodeposition of plutonium]. Many improvements in technique and methods and investigations along lines not explored are suggested by the present work. These will be undertaken as time permits, and reported at a later time."
Date: March 1, 1950
Creator: Schwendiman, L. C.
Object Type: Report
System: The UNT Digital Library
The Gasometric Determination of Nitrite and Sulfamate (open access)

The Gasometric Determination of Nitrite and Sulfamate

This report covers an investigation made to develop a gasometric determination that can determine 1.2 x 10-(-5) g. of nitrite with a precision (99% limits) of +/- 8%, and discusses how this procedure works.
Date: March 6, 1950
Creator: Carson, W. N.
Object Type: Report
System: The UNT Digital Library
Infrared Absorption Measurements Indicating Intermolecular Association of Water and Hexone (open access)

Infrared Absorption Measurements Indicating Intermolecular Association of Water and Hexone

This report analyzes infrared absorption measurements that were made in the regions of carbonyl band and hydroxyl band absorptions on solutions of water in hexone and water in acetone, confirming intermolecular association of water and hexone.
Date: March 8, 1950
Creator: Moore, R. H.
Object Type: Report
System: The UNT Digital Library
Corrosion of Stellite in MJ-1 Streams (open access)

Corrosion of Stellite in MJ-1 Streams

The following report provides data from completed tests for corrosion testing of stellite-T347 stainless steel test cylinders.
Date: March 8, 1950
Creator: Koenig, W. W.
Object Type: Report
System: The UNT Digital Library
The Determination of Tributyl Phosphate in Deodorized Shell Base with the Infrared Spectrometer (open access)

The Determination of Tributyl Phosphate in Deodorized Shell Base with the Infrared Spectrometer

The following report describes methods used to determine tributylphosphate in a deodorized shell base. An infrared absorption method is developed to emphasize toward determination of TBP in RCW streams, the organic waste streams.
Date: March 10, 1950
Creator: Moore, R. H.
Object Type: Report
System: The UNT Digital Library
Equilibrium Relationships for Stripping Uranium from Solutions of Tributyl Phosphate and Hydrocarbon Diluent (open access)

Equilibrium Relationships for Stripping Uranium from Solutions of Tributyl Phosphate and Hydrocarbon Diluent

Objective: "The laboratory equilibrium study RC-E-1 described in this report was carried out to obtain uranium equilibrium curves at various concentrations of nitric acid and of TBP."
Date: May 1, 1950
Creator: Clagett, Fred
Object Type: Report
System: The UNT Digital Library
Solubility relationships of acidified stored metal wastes (open access)

Solubility relationships of acidified stored metal wastes

The reports aims to determine the solubility limitation of concentrations of uranium in the food preparation step of the tributyl phosphate waste metal recovery process, and the subsequent solubilities in the RA column.
Date: March 24, 1950
Creator: Curtis, M. H.
Object Type: Report
System: The UNT Digital Library
Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin (open access)

Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin

Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."
Date: September 29, 1952
Creator: Schwope, A. D.; Muehlenkamp, G. T. & Chubb, Walston
Object Type: Report
System: The UNT Digital Library
Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin (open access)

Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin

Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."
Date: September 29, 1952
Creator: Schwope, A. D.; Muehlenkamp, G. T. & Chubb, Walston
Object Type: Report
System: The UNT Digital Library
Mechanical Properties of Iodide Zirconium Alloys (open access)

Mechanical Properties of Iodide Zirconium Alloys

Introduction: "The tensile properties, hot hardness, impact strength; and corrosion resistance of some arc-melted, iodide zirconium alloys have been determined. The alloys investigated include binary alloys of zirconium containing zero to five per cent tin, binary alloys of zirconium containing zero to 0.14 per cent nitrogen, and ternary alloys of zirconium containing tin and nitrogen, tin and uranium, and uranium and beryllium."
Date: November 1, 1952
Creator: Schwope, A. D. & Chubb, Walston
Object Type: Report
System: The UNT Digital Library
The Preparation of Beta Silicon Carbide (open access)

The Preparation of Beta Silicon Carbide

This report explores the production of beta silicon carbide, a low-temperature, cubic modification of cubic silicon carbide. The temperature, heating time, type of starting material, and proportion of starting materials were all varied in order to test yields of beta silicon carbide.
Date: December 29, 1952
Creator: Gambino, J. R.; Mixer, W. G., Jr.; Wagner, H. E. & Harman, Cameron G.
Object Type: Report
System: The UNT Digital Library
Evaluation of Oxidation-Resistant Ceramics for High-Temperature Reactor Elements (open access)

Evaluation of Oxidation-Resistant Ceramics for High-Temperature Reactor Elements

Abstract: "As a possible aid in the selection of ceramic materials for use in the fabrication of high-temperature reactor elements, the reported properties of 23 refractory oxidation-resistance ceramic compounds are tabulated. The thermal stresses and heat throughout capacities for nine of these compounds are estimated for conditions of steady heat flow and uniform heat generation in the temperature range of 1500 to 2500 F. The compounds studied have macroscopic thermal-neutron-absorption cross sections lower than 0.2 per centimeter. Data concerning the high-temperature stability of uranium compounds are tabulated for those with melting points above 2450 F."
Date: December 1, 1952
Creator: Harman, Cameron G.; Ferrell, Edward Francis.; Wagner, H. E. & Quirk, J. F.
Object Type: Report
System: The UNT Digital Library
Mechanical Properties of Zirconium-Tin Alloys (open access)

Mechanical Properties of Zirconium-Tin Alloys

Abstract: "The mechanical properties and corrosion resistance of induction-melted, zirconium-tin alloys have been determined. The alloys investigated contained from zero to five per cent tin and up to 0.3% carbon. The zirconium used was United States Bureau of Mines sponge zirconium. The mechanical properties investigated include the tensile, hot-hardness, and impact properties."
Date: December 22, 1952
Creator: Schwope, A. D. & Chubb, Walston
Object Type: Report
System: The UNT Digital Library
The Rolling of Uranium (open access)

The Rolling of Uranium

The following report discusses the method of rolling uranium rods and strips under various rolling conditions and the roll-separating force measured.
Date: December 30, 1952
Creator: Saller, Henry A.; Keeler, J. R. & Donley, R. J.
Object Type: Report
System: The UNT Digital Library
Electroplates on Thorium (open access)

Electroplates on Thorium

Abstract: "The protection of thorium in hot water was studied. Copper electrocladding on thorium offers promising protection against hot water. The corrosion of thorium in 95 C water was reduced appreciably by a thorium phosphate film. The results of this abbreviated investigation offer a basis for the development of a method of protecting thorium at elevated temperatures in corrosive media."
Date: January 9, 1953
Creator: Beach, John G.; Schickner, W. C.; Vaaler, L. E. & Faust, Charles L.
Object Type: Report
System: The UNT Digital Library
The Fabrication of Thorium Tubes (open access)

The Fabrication of Thorium Tubes

Abstract: "Thorium tubes were cold drawn from extruded tube stock and also from drilled hot-rolled rod. Total reductions up to approximately 85 per cent were accomplished by conventional tube-drawing methods, without an intermediate anneal. The hard-drawn tubes had high tensile strength, but the ductility, as indicated by flaring and flattening tests, was low."
Date: January 16, 1953
Creator: Saller, Henry A. & Keeler, J. R.
Object Type: Report
System: The UNT Digital Library