Improved Zirconium Alloys Quarterly Report: October - December 1961 (open access)

Improved Zirconium Alloys Quarterly Report: October - December 1961

Quarterly report describing the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between October 1 to December 31, 1961 and was conducted by the United States and the European Atomic Energy Community (EURATOM).
Date: January 12, 1962
Creator: Weinstein, Daniel & Holtz, F. C.
Object Type: Report
System: The UNT Digital Library
The Boron-Carbon System: Quarterly Report Number 2, August - October 1960 (open access)

The Boron-Carbon System: Quarterly Report Number 2, August - October 1960

Abstract: A definitive investigation of the boron-carbon equilibrium system is being made by X-ray diffraction, metallographic, and thermal analytical techniques. Additional baron-carbon alloys have been prepared by sintering and arc-melting compacts prepared from boron and high-purity graphite. Metallographic examinations of these alloys are in agreement with alloys previously preapred from lampblack. X-ray investigation of sintered compacts indicates that the solubility range of boron carbide extends almost to pure boron. Boron of various purities has been annealed for times up to four hours, but no structure other than beta-rhombohedral has been detected. Very high purity boron (10 ppm impurity) has been obtained for the study of allotropy and the equilibrium relationships at very dilute carbon contents.
Date: November 8, 1960
Creator: Elliott, Rodney P. & Van Thyne, R. J.
Object Type: Report
System: The UNT Digital Library
The Boron-Carbon System: Quarterly Report Number 3, November 1960 - January 1961 (open access)

The Boron-Carbon System: Quarterly Report Number 3, November 1960 - January 1961

Abstract: A definitive investigation of the boron-carbon equilibrium system is being made by X-ray diffraction, metallographic, and thermal analytical techniques. On the basis of metallographic and X-ray diffraction studies it is concluded that boron carbide has a range of solubility from approximately 10 to 20 atomic per cent carbon at 1500 degrees to 2000 degrees Celsius. The melting point of the carbide-graphite eutectic has been established as 2325-2350 degrees Celsius. No reversible allotropy of the beta-rhombohedral structure has been observed. The solubility of carbon in boron is very small. The melting point of dilute carbon alloys is found to be essentially the same as that of pure boron (2040 degrees to 2050 degrees). No metallographic evidence of a three-phase reaction of dilute alloys is observed.
Date: February 6, 1961
Creator: Elliott, Rodney P.
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
Delayed Failure Hydrogen Embrittlement of Zirconium: Quarterly Report Number 1, September - December 1961 (open access)

Delayed Failure Hydrogen Embrittlement of Zirconium: Quarterly Report Number 1, September - December 1961

Abstract: "The purpose of this investigation is to determine the extent to which zirconium exhibits delayed failure (static fatigue) as caused by a combination of absorbed hydrogen and applied stress. Both notched and unnotched specimens of unalloyed zirconium and Zircaloy-2 are being initially hydrogenated to 200 ppm by means of a modified Sieverts apparatus, and delayed failure studies are proceeding at room-temperature. Thus far only preliminary data on unnotched, unalloyed zirconium are available; at the 200 ppm hydrogen level, this material appears to be relatively insensitive to delayed failure at room-temperature."
Date: January 3, 1962
Creator: Weinstein, Daniel & Holtz, F. C.
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
Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Eighth Letter Report, June 1 to August 1, 1959 (open access)

Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Eighth Letter Report, June 1 to August 1, 1959

Introduction: "This is the eighth letter report on ARF Project C 127, entitled "Preliminary Studies of Scavenging Systems Related to Radioactive Fallout." This report covers the period from June 1 to August 1, 1959."
Date: August 20, 1959
Creator: Stockham, John D. & Rosinski, John
Object Type: Report
System: The UNT Digital Library
Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Ninth Letter Report, August 1 to October 1, 1959 (open access)

Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Ninth Letter Report, August 1 to October 1, 1959

Introduction: "This is the ninth letter report on ARF Project C 127, entitled "Preliminary Studies of Scavenging Systems Related to Radioactive Fallout." This report covers the period from August 1 to October 1, 1959."
Date: October 26, 1959
Creator: Stockham, John D. & Rosinski, John
Object Type: Report
System: The UNT Digital Library
Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Tenth Letter Report, October 1 to December 1, 1959 (open access)

Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Tenth Letter Report, October 1 to December 1, 1959

Introduction: "This is the tenth letter report on ARF Project C 127, entitled "Preliminary Studies of Scavenging Systems Related to Radioactive Fallout." This report covers the period from October 1 to December 1, 1959."
Date: December 18, 1959
Creator: Stockham, John D. & Rosinski, John
Object Type: Report
System: The UNT Digital Library
Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Summary Report, April 1, 1959 to April 29, 1960 (open access)

Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Summary Report, April 1, 1959 to April 29, 1960

This is the summary report on the ARF Project C 127, entitled "Preliminary Studies Related to Radioactive Fallout", covering the period from April 1, 1959, to April 29, 1960.
Date: April 29, 1960
Creator: Rosinski, John & Stockham, John D.
Object Type: Report
System: The UNT Digital Library
Studies of reactor containment : bi-monthly progress report, July to August 1962 (open access)

Studies of reactor containment : bi-monthly progress report, July to August 1962

A report about 3 tasks which are undergone in this project. These tasks pertain to preparing computer codes for calculations of wave transmission in layered composites of materials, the performance of gas shock impingement experiments, and analyzing previously obtained experimental data using a liquid driven shock tube.
Date: 1962
Creator: Lieberman, P. & Zaker, T. A.
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
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.
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
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.
Object Type: Report
System: The UNT Digital Library
Topical Report on Chemical Process to Recover Uranium from Phosphate Rock (open access)

Topical Report on Chemical Process to Recover Uranium from Phosphate Rock

The following report summarizes research done on dissolving uranium from phosphate rock and superphosphate and recovering it from solution in a more concentrated form.
Date: November 15, 1947
Creator: Igelsrud, Iver
Object Type: Report
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

Abstract: "Dissolution of carnotite in several readily liquefiable gases, including ammonia, sulfur dioxide, chlorine, and nitrogen dioxide, was found to be negligible, even in the presence of uranium complexing agents. No low-boiling liquids have been found which will dissolve carnotite directly. Treatment with various sulfur chloride will convert carnotite to a form soluble in water or in certain organic solvents. Also, carnotite can be readily dissolved in HCl-acidified ethanol, methanol, or acetone. Amenability tests on nine western ores with HCl-methanol solvent indicated that uranium extractions greater than 90 per cent could be obtained if sufficient acid was used to insure some free acidity in the pregnant liquor. Temple Mountain and Sinbad-Muddy River ores were exceptions to this, uranium extractions being only about 50-60 per cent. Vanadium extractions were invariably lower than uranium extractions. Chemical analyses are presented for nine western ores."
Date: January 15, 1953
Creator: Ewing, R. A.; Pobereskin, M.; Kiehl, S. J.; Foley, D. D.; Filbert, Robert B.; Kimball, R. B. et al.
Object Type: Report
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.
Object Type: Report
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.
Object Type: Report
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.
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
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.
Object Type: Report
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.
Object Type: Report
System: The UNT Digital Library