The solubility of sodium phosphate in sodium hydroxide solutions (open access)

The solubility of sodium phosphate in sodium hydroxide solutions

A report about how trisodium phosphate can be most satisfactorily removed from sodium hydroxide solutions at 40 percent sodium hydroxide concentration, or higher, the temperature being practically immaterial, or it can be removed antisfactorily from 15 to 30 per cont sodium hydroxide at 25°C
Date: 1950
Creator: Youtz, M. A.; Warren, F. A. & Bearse, A. E.
System: The UNT Digital Library
Topical report on anion-exchange studies on the separation and purification of uranium and thorium (open access)

Topical report on anion-exchange studies on the separation and purification of uranium and thorium

A report which describes the separation of uranium from thorium in carbonate, hydrochloric acid, and sulfuric acid solutions by anion-exchange resins.
Date: 1950
Creator: Poirier, R. H. & Bearse, A. E.
System: The UNT Digital Library
Topical report on examination of residues from the nitric acid digestion of pitchblende (open access)

Topical report on examination of residues from the nitric acid digestion of pitchblende

A report about an investigation started to determine the compounds and/or minerals present in the residue resulting from nitric acid digestion of ore. Emphasis was placed on determining the compounds and/or minerals containing boron.
Date: 1950
Creator: Langston, B.; Tangel, O. F. & Richardson, A. C.
System: The UNT Digital Library
Estimated Manufacturing Costs for the Recovery of Thorium and Uranium from Monazite Sand (open access)

Estimated Manufacturing Costs for the Recovery of Thorium and Uranium from Monazite Sand

Abstract: "Costs have been estimated for the production of uranium and pure thorium from monasite concentrates by a process involving (1) reaction of monasite with caustic soda, (2) dissolution of the hydrous oxides in hydrochloric acid, (3) separation from the bulk of the rare earths by hydroxide precipitation of thorium and uranium, and (4) purification by solvent extraction."
Date: September 15, 1950
Creator: Calkins, G. D. & Filbert, R. B., Jr.
System: The UNT Digital Library
Zirconium Research and Development : Progress Report (open access)

Zirconium Research and Development : Progress Report

From introduction: "This is the ninth monthly report, BMI-514, under Contract No. AT(30-1)-771 on "Zirconium Research and Development". The report covers the work period from September 15, 1950, to October 15, 1950. Work is continuing on the preparation of large-diameter zirconium crystal bars in the 16-inch-diameter de Boer unit. Crystal bars up to 1-5/16 inches in diameter and 8 feet long have been prepared in this unit."
Date: October 15, 1950
Creator: Bulkowski, H. H.; Sebenick, J. J.; Campbell, Ivor E. & Gonser, B. W.
System: The UNT Digital Library
The thermal and electrical conductivities of zirconium and its alloys (open access)

The thermal and electrical conductivities of zirconium and its alloys

A report which intends to present an empirical formula, based on available experimental data, to correlate the thermal and electrical conductiviities of sirconium and sirconium alloys.
Date: 1951
Creator: Bing, George; Fink, F. W. & Thompson, H. B.
System: The UNT Digital Library
Mineralogical Examination of Pitchblende Concentrates and Nitric Acid Digest Residues (open access)

Mineralogical Examination of Pitchblende Concentrates and Nitric Acid Digest Residues

This report has two parts to it discussing mineralogical examination of pitchblende concentrates and nitric acid digest residues. Part I gives the results of a cursory examination with the petrographic microscope of samples of pitchblende concentrates and residues to see if there is a relationship between the mineral composition of the samples and the filterability of the residue. Part II gives a revaluation of the data in Report BMI-241 on the mineral composition of two residues from the nitric acid digestion of pitchblende concentrates at the Rallinckrodt Chemical Works.
Date: February 9, 1951
Creator: Scott, D. W.; Tangel, O. F. & Richardson, A. C.
System: The UNT Digital Library
Engineering Properties of High-Density Concretes (open access)

Engineering Properties of High-Density Concretes

From summary: "Methods were developed for measuring various engineering properties of high-density concretes. Data are presented on selected thermal properties of a limonite-iron concrete and the mechanical properties of the limonite-iron concrete, a magnesium oxychloride concrete, and a Portland cement concrete containing steel punchings and shot (no limonite)."
Date: May 1951
Creator: Snyder, M. Jack; Burkart, C. A. & Clegg, John 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
Zirconium Pilot Plant Research and Development Progress Report (open access)

Zirconium Pilot Plant Research and Development Progress Report

The following progress report was compiled by the research and development division of the zirconium pilot plant. This report discusses two iodination and deposition runs that were completed as of August 20, 1951, as well as the third iodination run that uses a vaporizer condenser that condenses approximately 40 pounds of zirconium iodide.
Date: September 20, 1951
Creator: Accountius, O. E.; Black, D. G.; Dryden, C. E.; Finney, B. C.; Gruber, B. A.; Jurevic, W. G. et al.
System: The UNT Digital Library
The Fabrication and Compatibility of Metallic Fuel Elements for High-Temperature Service (open access)

The Fabrication and Compatibility of Metallic Fuel Elements for High-Temperature Service

From summary: "This report covers an experimental investigation into the fabrication of various potential fuel-element materials and the testing of these materials for compatibility with structural metals at 1090 C (2000 F)."
Date: October 8, 1951
Creator: Saller, Henry A. & Stacy, J. T.
System: The UNT Digital Library
Zirconium Pilot Plant Research and Development Progress Report (open access)

Zirconium Pilot Plant Research and Development Progress Report

The following report studies the effect of flow rates and deposition pressure on the zirconium deposition in the zirconium pilot plant with the use of a Hilco oil purifier for the vacuum pumps that permitted studies to continue through the month.
Date: November 20, 1951
Creator: Dryden, C. E.; Accountius, O. E.; Black, D. G.; Finney, B. C.; Gruber, B. A.; Jurevic, W. G. et al.
System: The UNT Digital Library
Use of electrical measurements to detect differences among uranium tetrafluoride samples : final report (open access)

Use of electrical measurements to detect differences among uranium tetrafluoride samples : final report

A report which contains a summary of the research during the period September 1, 1951, to January 31, 1952, on the utilization of electrical measurements to detect chemical and physical differences in various samples of UF4.
Date: 1952
Creator: Reynolds, D. C. & Middleton, A. E.
System: The UNT Digital Library
Tungsten-Arc Welding of Ames Thorium and Thorium Alloys (open access)

Tungsten-Arc Welding of Ames Thorium and Thorium Alloys

This report follows an investigation made on the welding of Ames thorium by the inert-gas-shielded tungsten-arc process as the first part of a program on the joining of thorium. This program is part of a broader research program to develop the technology of thorium.
Date: January 15, 1952
Creator: Monroe, Robert E.; Martin, D. C. & Voldrich, C. B.
System: The UNT Digital Library
Identification of Slag Constituents from Uranium Metal Production Bombs (open access)

Identification of Slag Constituents from Uranium Metal Production Bombs

Abstract: "X-ray and microscopic examination of slags from uranium metal production bombs which gave good and bad yields in the plant at St. Louis have indicated the significance of uranium oxide formation. Apparently the oxide (UO2) results from reaction of the UF4 with linear material, particularly with moisture in the liner."
Date: January 31, 1952
Creator: Vaughan, D. A.; Cocks, G. G. & Schwartz, C. M.
System: The UNT Digital Library
Hydroxides as Moderator Coolants in Power-Breeder-Reactors (open access)

Hydroxides as Moderator Coolants in Power-Breeder-Reactors

The following report describes work that was udertaken to determine whether a homogeneous breeder reactor using an alkili metal hydroxide solution is capable of breeding.
Date: March 26, 1952
Creator: Dayton, Russell Wendt & Chastain, Joel W.
System: The UNT Digital Library
The Determination of Rare Earths in Thorium (open access)

The Determination of Rare Earths in Thorium

Abstract: "A quantitative method for the determination of individual rare earths in thorium down to a level of 0.05 ppm, is described. The procedure consists of a chromatographic cellulose-columns separation followed by a solution-type spectrographic determination. Values are given for the recovery of a number of rare earths using this combined procedure."
Date: May 15, 1952
Creator: Center, E. J.; Henry, W. M. & Householder, R. D.
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
Experimental Fabrication of a Lightweight Control Rod (open access)

Experimental Fabrication of a Lightweight Control Rod

Abstract: "The possibility of fabricating a lightweight control rod from one of several high cross-section materials was investigated. The major effort was directed toward the development of a titanium-clad rod containing a composite core of 25 weight per cent Gd2O3 in a matrix of titanium. Experimentation on both subscale and full-scale control-rod cores showed that the fabricating behavior of the two was not analogous. To roll the full-scale core successfully, it was necessary to lower the oxide content to 17 weight per cent. Subscale investigations were also carried out on titanium-cadmium, titanium-lanthanum, and titanium-gadolinium alloys."
Date: July 1, 1952
Creator: Saller, Henry A.; Stacy, J. T. & Keller, D. L.
System: The UNT Digital Library
Beryllia and Beryllia-Beryllium Bodies for Moderating Cores in Fuel Elements (open access)

Beryllia and Beryllia-Beryllium Bodies for Moderating Cores in Fuel Elements

From introduction: This report presents the results of the two phases of the work: study of the compatibility of beryllia bodies with a coating material, molybdenum; and studies of beryllia-beryllium body fabrication.
Date: July 31, 1952
Creator: Long, R. E.; Duckworth, W. H.; Saller, Henry A.; Stacy, J. T.; Miller, R. A. & Schofield, H. Z.
System: The UNT Digital Library
An Application of the Concepts of Particle Packing to the Consolication of Silicon Carbide Powders (open access)

An Application of the Concepts of Particle Packing to the Consolication of Silicon Carbide Powders

From introduction: Silicon carbide is being considered as a basis material for nonmetallic fuel elements because of its high thermal conductivity, low nuclear cross section, high resistance to thermal rupture, and high degree of stability at high temperature in air. A requirement of the fuel elements is that they be thin and have as low porosity as possible. One shape of element under consideration is 0.050 to 0.070 inch thick by a few inches in width and breadth.
Date: August 15, 1952
Creator: Harman, Cameron G.; Shinn, J., Jr. & Wagner, H. E.
System: The UNT Digital Library
Hydrogen Embrittlement of Zirconium (open access)

Hydrogen Embrittlement of Zirconium

Abstract: "The amount of hydrogen normally present in zirconium and zirconium alloys suffices to reduce their ductility greatly in an impact test at room temperature, after slow cooling from 600 F. Quenching from 600 F or above gives high impact strength, as does removal of hydrogen by high-temperature vacuum annealing. This report discusses the evidence on hydrogen embrittlement, the diffusion, solid solubility, and equilibrium pressure of hydrogen of hydrogen in zirconium, the microstructure, and the effects of hydrogen and heat treatment on the mechanical properties of zirconium."
Date: August 22, 1952
Creator: Dayton, Russell Wendt; Schwope, A. D.; Muehlenkamp, G. T.; Saller, Henry A.; Dickerson, R. F.; Schwartz, C. M. et al.
System: The UNT Digital Library
Creep of 2S-O Aluminum Sheet at 500 and 550 C (open access)

Creep of 2S-O Aluminum Sheet at 500 and 550 C

Abstract: "Creep and creep-rupture tests were made on 25-O aluminum sheet at temperatures of 500 and 550 C. The estimated stresses that will produce 0.5 per cent deformation and rupture in 10,000 hours at 400, 450, 500, and 550 C (data at 400 and 450 C are from BMI-T-29, dated June 9, 1950) are presented."
Date: September 11, 1952
Creator: VanEcho, J. A.; Simmons, W. F. & Cross, H. C.
System: The UNT Digital Library