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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 Preparation of Large-diameter Zirconium Crystal Bar by the De Boer Process (open access)

The Preparation of Large-diameter Zirconium Crystal Bar by the De Boer Process

This report discusses the production of large-diameter zirconium crystal bars in a 16 inch diameter, Hastelloy B, de Boer unit in order to increase production efficiency.
Date: March 6, 1951
Creator: Bulkowski, H. H.; Beale, L. C.; Sebenick, J. J.; Campbell, Ivor E. & Gonser, B. W.
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
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
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
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
The Rolling of Thorium Rod (open access)

The Rolling of Thorium Rod

Report discussing the rolling of thorium rods. Abstract: "Thorium rods, 1-7/16 inch in diameter, were rolled from Ames castings. The billets were roughed down in diamond-grooved rolls and finished in hand-rounding rolls. Remelted chips as well as primary-metal castings were rolled, and both yielded satisfactory rods. The surface quality of the rods was generally excellent, and the machined slugs were free of seams."
Date: December 19, 1951
Creator: Saller, Henry A.; Keeler, J. R. & Donley, R. J.
System: The UNT Digital Library
A Study of Thorium-Base Alloys (open access)

A Study of Thorium-Base Alloys

Report discussing studies testing various thorium alloys consisting of either Ames thorium and up to 5% of various additions or Ames thorium and up to 50% uranium. Effects of molybdenum additions for fusion welding, and cold-work strengthening were also tested. Methods, experimental data, and discussion is included.
Date: December 26, 1951
Creator: Goldhoff, R. M.; Ogden, Horace R. & Jaffee, Robert Isaac, 1917-
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
Progress Report for the Month of January, 1952 (open access)

Progress Report for the Month of January, 1952

This progress report of the Battelle Memorial Institute covers information in many categories. These include development of ceramic fuel elements, general ceramics, uranium and its alloys, thorium and its alloys, development of metallic fuel elements and assemblies, metals and alloys for reactor components, miscellaneous metallurgical work, liquid coolants and fuels, reactor engineering studies, and mechanism development.
Date: February 1, 1952
Creator: Russell, H. W.; Nelson, H. R. & Dayton, R. W.
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
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
Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores (open access)

Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores

This report describes progress in testing nonaqueous methods for extracting uranium and vanadium from Western ores. Acetone leaches were found to be effective.
Date: January 20, 1954
Creator: Ewing, R. A.; Kiehl, S. J., Jr.; Kimball, R. B. & Bearse, A. E.
System: The UNT Digital Library
Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores (open access)

Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores

The following progress reports continues the investigation of the HCl-acetone process for extracting uranium, discovering that it is applicable to most Western ores, yielding high uranium recoveries. The economics of the process have been improved by substitution of sulfuric acid for part of the hydrochloric acid requirements.
Date: April 20, 1954
Creator: Ewing, R. A.; Pobereskin, M.; Kiehl, S. J.; Foley, D. D.; Filbert, Robert B.; Kimball, R. B. et al.
System: The UNT Digital Library
Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores (open access)

Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores

This report describes progress regarding construction of a small pilot plant and a five-step process involving hydrochloric-sulfuric acid treatment and acetone extraction.
Date: October 20, 1954
Creator: Ewing, R. A.; Foley, D. D.; Filbert, Robert B., Jr. & Bearse, A. E.
System: The UNT Digital Library
Final Report on Nonaqueous Extractive Methods for Western Uranium Ores (open access)

Final Report on Nonaqueous Extractive Methods for Western Uranium Ores

This report discusses tests of several nonaqueous extractive methods meant to leach Western ores of uranium and vanadium. Explanations of different methods are given as well as their extraction results.
Date: January 31, 1955
Creator: Ewing, R. A.; Kiehl, S. J., Jr. & Bearse, A. E.
System: The UNT Digital Library
Progress Report on the Concentration of Pitchblende (open access)

Progress Report on the Concentration of Pitchblende

Abstract: "The results of leaching studies on sulphide froth products obtained from the flotation of high-sulphur pitchblende are presented. The distribution of molybdenum in flotation products is also given. The flotation test at Middlesex is evaluated."
Date: December 31, 1950
Creator: Wesner, A. L.; Tangel, O. F. & Richardson, A. C.
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
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
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
Final Report on Purification of Thorium Nitrate by Solvent Extraction With Tributyl Phosphate: 2. Mixer-Settler Pilot Plant Investigations (open access)

Final Report on Purification of Thorium Nitrate by Solvent Extraction With Tributyl Phosphate: 2. Mixer-Settler Pilot Plant Investigations

From abstract: "This report describes the construction and operation of a mixer-settler pilot plant for the purification of mantle-grade thorium nitrate. The liquid-liquid extraction process utilized 30% tributyl phosphate - 70% 'Solvesso-100' as the organic solvent and nitric acid as the salting agent. Continuous steady-state operation of the equipment was demonstrated, with very good recovery of thorium."
Date: July 31, 1952
Creator: Burkhart, C. A.; Foley, D. D.; Retzke, F. A.; Filbert, Robert B., Jr. & Clegg, John W.
System: The UNT Digital Library