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Welded Repair of Fill and Drain Holes in High-Carbon Steel Gas Storage Cylinders (open access)

Welded Repair of Fill and Drain Holes in High-Carbon Steel Gas Storage Cylinders

Report discussing the results of fill and drain holes for hydrostatic pressure tests on head knuckle radius of forged-steel gas storage cylinders.
Date: November 5, 1964
Creator: Thompson, J. C. & Lambert, F. J.
Object Type: Report
System: The UNT Digital Library
Effects of Major Parameters on Cycle Efficiency and Cost for a Gas-Cooled Reactor Turbine Power Plant (open access)

Effects of Major Parameters on Cycle Efficiency and Cost for a Gas-Cooled Reactor Turbine Power Plant

Cycle study performed on a closed loop Brayton cycle incorporating a gas-cooled nuclear reactor, regeneration, and compressor intercooling. The purpose of the study was to determine the effect of various cycle parameters on efficiency and cost.
Date: October 5, 1962
Creator: Miskell, R. V.
Object Type: Report
System: The UNT Digital Library
A Study of the Feasibility of Using Scintillating Fibers for Low Energy Beta Counting: Quarterly Report Number 1, June - September 1961 (open access)

A Study of the Feasibility of Using Scintillating Fibers for Low Energy Beta Counting: Quarterly Report Number 1, June - September 1961

From introduction: "A detector system with the advantages of a liquid counter, but without the severe requirements on sample preparations, has been devised and is the basis of the present experimental investigation."
Date: January 5, 1962
Creator: Preston, C.
Object Type: Report
System: The UNT Digital Library
Grain Refinement of the As-Cast Uranium-5 w/o Chromium Alloy by Ternary Additions (open access)

Grain Refinement of the As-Cast Uranium-5 w/o Chromium Alloy by Ternary Additions

Abstract: "Refinement of grain size of the base uranium-chromium eutectic alloy (uranium-5 w/o chromium) by ternary additions is discussed. Thirteen additions to the base alloy were investigated, and three additions were found to exhibit worthwhile grain-refinement tendencies. The three alloys, uranium-5 w/o chromium-0.2 w.o molybdenum, uranium-5 w/o chromium-0.2 w/o germanium, and uranium-5 w/o chromium-0.2 w/o niobium, were heat treated to produce final grain-size structures of between 0.015 and 0.033 mm."
Date: July 5, 1955
Creator: Saller, Henry A.; Dickerson, Ronald F.; Murr, William E. & Bauer, Arthur A.
Object Type: Report
System: The UNT Digital Library
Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1952 (open access)

Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1952

This quarterly progress report details ongoing work at the Oak Ridge National Laboratory as part of the Aircraft Nuclear Propulsion Project. Topics of discussion include reactor theory and design, shielding research, materials research, appendixes with information on ongoing analytical chemical studies.
Date: August 5, 1952
Creator: Briant, R. C.; Buck, J. H.; Miller, A. J. & Cottrell, W. B.
Object Type: Report
System: The UNT Digital Library
Decontamination of ORNL Purex Pilot Plant (open access)

Decontamination of ORNL Purex Pilot Plant

From abstract: "This report describes the decontamination of Oak Ridge National Laboratory Purex Pilot Plant facilities and presents an appraisal of the decontaminating techniques and reagents which were employed."
Date: May 5, 1952
Creator: Wood, H. P.
Object Type: Report
System: The UNT Digital Library
A Preliminary Report on Health Physics Problems at the Brookhaven Alternating Gradient Synchrotron (AGS) (open access)

A Preliminary Report on Health Physics Problems at the Brookhaven Alternating Gradient Synchrotron (AGS)

This report discusses the alternating gradient synchrotron at Brookhaven National Laboratory and provides a preliminary discussion on experiences to date and experiments in progress.
Date: March 5, 1962
Creator: Cowan, F. P.
Object Type: Report
System: The UNT Digital Library
Preliminary Reconnaissance Work in the Rattlesnake Area, Apache County, Arizona (open access)

Preliminary Reconnaissance Work in the Rattlesnake Area, Apache County, Arizona

From introduction: The Bluff-Salt Wash contact was mapped on aerial photographs. Mines and prospects were also plotted on the photos. The mines and prospects were studied and a brief description of the mineralization and its occurrence was written. These field notes, which will be given to Hatfield and party, contain data on the presence of carbon and fossil logs, lithology of the gangue rock, sedimentary structures, etc. Regional structure and evidence for igneous activity were also noted.
Date: September 5, 1952
Creator: Hill, John F. & Blagbrough, John W.
Object Type: Report
System: The UNT Digital Library
Preshot and Postshot Safety Survey of Oil and Gas Facilities, Baxterville Field, Mississippi, Final Report (open access)

Preshot and Postshot Safety Survey of Oil and Gas Facilities, Baxterville Field, Mississippi, Final Report

From introduction: Oil and gas wells and related facilities of the Baxterville field were surveyed to document any physical changes resulting from the Salmon Event. All such structures within a 5-mile radius of Ground Zero were examined and photographed in detail.
Date: August 5, 1965
Creator: Ward, Don C.
Object Type: Report
System: The UNT Digital Library
Removal of Deuterated Boric Acid From Deuterium Oxide Solution by Ion Exchange Resin (open access)

Removal of Deuterated Boric Acid From Deuterium Oxide Solution by Ion Exchange Resin

Introduction: "Because of the importance of the value of the transport mean free path of thermal neutrons in deuterium oxide, Kash and Woods proposed to redetermine this value in deuterium oxide (99.4 atom-percent deuterium, by an extrapolation method. Kash and Woods thought that the low value of the transport mean free path might be a source of error. This paper relates studies of procedures by which (1) boron material would be dissolved in high content deuterium oxide without adding foreign atoms, particularly hydrogen atoms which might adversely affect the test, (2) the boron content of the deuterium oxide solvent may be determined, (3) ion exchangers may be deuterized and de-deuterized, and (4) ion exchange may remove specific ions from solution."
Date: January 5, 1954
Creator: Silverman, L.
Object Type: Report
System: The UNT Digital Library
Extraction of Uranyl Nitrate and Thorium Nitrate by Organic Solvents (open access)

Extraction of Uranyl Nitrate and Thorium Nitrate by Organic Solvents

Abstract. The separation of uranyl nitrate from aqueous solutions of 0.635 M thorium nitrate, 3 M nitric acid and 3 M calcium nitrate by extraction with organic solvents has been investigated. Solvents which gave good separations were 2-tthyl hexyl acetate, ethyl benzoate, n-butyl either and beta-beta- dichloroethyl ether. In general, higher esters, ethers and alcohols are better for separating uranium from thorium that the lower homologues. Several solvents were tested at lower nitric acid concentrations. Dibutyl cellosolve gave a very good separation when the solution was 0.1 M nitric acid. Of the solvent mixtures studied that of equal parts of n-butyl ether and dibutyl cellosolve gave a good separation.
Date: November 5, 1945
Creator: Johnson, O. & Newton, A. S.
Object Type: Report
System: The UNT Digital Library
Precipitation of Thorium Oxalate from Nitric Acid Solutions (open access)

Precipitation of Thorium Oxalate from Nitric Acid Solutions

Introduction. It has been known for a long time that thorium is precipitated by oxalic acid in acid solutions, but a survey of the literature showed no study of the limits of the acidity and oxalic acid excess which yield quantitative results. V. I. Spitzin reports on the solubility of thorium oxalate in varying concentrations of several acids, but the effect of an excess oxalic acid is not included. Since solutions are sometimes presented for analysis that contain more than the recommended two per cent mineral acid, it would be advantageous to be able to quantitatively remove the thorium without otherwise altering the solutions. This was especially of interest in solutions containing bismuth, since it was hoped that some amounts of thorium could be precipitated in nitric acid solutions containing large quantities of bismuth. In removing the bismuth, first by a bismuth oxychloride precipitation, thee is every opportunity for carrying of the thorium.
Date: October 5, 1945
Creator: Ayers, A. S.
Object Type: Report
System: The UNT Digital Library
Acute Histopathological Effects of Single Doses of Slow Neutrons on Mice (open access)

Acute Histopathological Effects of Single Doses of Slow Neutrons on Mice

The following report provides information conducted during histological observations made on the anatomy of female mice who have been exposed to 400 arbitrary units of slow neutrons.
Date: February 5, 1947
Creator: Snider, R.
Object Type: Report
System: The UNT Digital Library
An Ion Chamber for the Determination of Small Amounts of Tritium in Other Gases (open access)

An Ion Chamber for the Determination of Small Amounts of Tritium in Other Gases

This report helps determine tritium in the range of 0.1 to 100% in other gases using an ion chamber that is analyzed within this report.
Date: May 5, 1951
Creator: Mattraw, H. C.
Object Type: Report
System: The UNT Digital Library
Reconnaissance of Henry Mountains Area, Wayne and Garfield Counties, Utah (open access)

Reconnaissance of Henry Mountains Area, Wayne and Garfield Counties, Utah

From introduction: A trip into the Henry Mountains area occupied the days from March 6 to 9, 1951, inclusive, excepting March 7, which was used to examine Reo Hunt's deposit in Poison Spring Wash. Observations were made on stratigraphy, regional geology, and the locations of the known deposits of uranium and vanadium.
Date: April 5, 1951
Creator: Reinhardt, E. V.
Object Type: Report
System: The UNT Digital Library
High Pressure Pump Seal Development (open access)

High Pressure Pump Seal Development

"Test results indicated that graphite is not suitable for seal face material. A program to evaluate various materials and seal face geometries was initiated. A seal run using nucerite-bearium combination was carried on for six hours."
Date: March 5, 1962
Creator: Zanoni, P. J.
Object Type: Report
System: The UNT Digital Library
Introduction to Diffusion Theory and to Pile-Theory (open access)

Introduction to Diffusion Theory and to Pile-Theory

The following report describes and foretells the situation in medium in which neutrons are being (a)produced as fast neutrons, (b) slowed down to thermal speeds by impacts with nuclei, and (c) absorbed by nuclei in such a manner that sometimes fresh fast neutrons appear at the place where a thermal neutron has just appeared.
Date: October 5, 1944
Creator: Darrow, Karl K.
Object Type: Report
System: The UNT Digital Library
Feasibility Study of a Neutron Flux Bolometer (open access)

Feasibility Study of a Neutron Flux Bolometer

Abstract: "A small low impedance flux monitoring device has been built which utilizes the heating (and consequent chance in resistance) of a boron coated platinum wire. Feasibility tests in the Argonne-GP-3 reactor indicate that it may develop into a wide range instrument, particularly useful at high flux levels. Design and constructional details of the bolometer and its associated circuits are given. The circuitry is somewhat unique since it is in effect an all electronic self-balancing bridge. Future lines of research are suggested to solve some of the remaining problems."
Date: September 5, 1951
Creator: Leonard, Robert R.
Object Type: Report
System: The UNT Digital Library
The Uranium-Titanium Alloy System (open access)

The Uranium-Titanium Alloy System

Abstract: "A uranium-titanium constitution diagram is presented. There is complete solid solubility between titanium and gamma uranium above about 2100 F. Only one compound exists in the system. It has a hexagonal structure based on U2Ti. It has a fairly wide range of stability, particularly on the titanium side. Beta-titanium solid solution decomposes eutectoidally into alpha titanium and compound at 1150 F. Eutectoid composition is about 72 atomic per cent titanium. Gamma-uranium solid solution decomposes eutectoidally at 1325 F into beta uranium and compound. Eutectoid composition is about 6 atomic per cent titanium. Beta uranium and compound react peritectoidally at 1233 F to give alpha uranium. Solubility of titanium in alpha and beta uranium is low as is the solubility or uranium in alpha titanium."
Date: November 5, 1952
Creator: Udy, Murray C. & Boulger, Francis W.
Object Type: Report
System: The UNT Digital Library
Neutron Total Cross Section for Bismuth and Uranium Between 45 and 160 Mev (open access)

Neutron Total Cross Section for Bismuth and Uranium Between 45 and 160 Mev

"Neutron total cross sections for bismuth and uranium have been measured in a good geometry transmission experiment, using a time-of-flight instrumentation. The source of neutrons was the stripped deuteron beam of the 184-inch synchrocyclotron. The results are shown in Fig. 1. Uncertainties are shown in terms of standard deviations, due to counting statistics only, and to energy channel width."
Date: August 5, 1953
Creator: Linlor, William I., 1915- & Ragent, Boris
Object Type: Report
System: The UNT Digital Library
Analysis of Lid Tank Neutron Data for Lead and Iron (open access)

Analysis of Lid Tank Neutron Data for Lead and Iron

Abstract: An analysis of the lid tank neutron data for Pb-H2O and Fe-H2O is made. "Effective" fast neutron cross sections for the metals are obtained. This is based on the "one collision theory" of shielding. Values are 3.4 barns for Pb and 2.0 barns for Fe. These compare very well with those obtained by Albert and Welton based on other lid tank data and another method of calculation.
Date: January 5, 1951
Creator: Podgor, S.
Object Type: Report
System: The UNT Digital Library
Factors Affecting Properties of Extruded Compacts of Crystal Bar Zirconium (open access)

Factors Affecting Properties of Extruded Compacts of Crystal Bar Zirconium

The following report analyzes various experiments made to discover factors that may affect properties of extruded compacts of crystal bar zirconium.
Date: December 5, 1955
Creator: Arnold, Samuel V.
Object Type: Report
System: The UNT Digital Library
Materials Testing Reactor Project: Coffins and Coffin Handling, Design Report No. 21 (open access)

Materials Testing Reactor Project: Coffins and Coffin Handling, Design Report No. 21

The following report discusses special shielded containers, called coffins, that are used for removing beam hole plugs from the reactor, transporting them to plug storage and inserting them therein. This report focuses on the handling of dummy and experimental beam hole plugs.
Date: December 5, 1949
Creator: Paleczny, M. P.
Object Type: Report
System: The UNT Digital Library
Maximum Allowable Concentration for Air-Borne Beta Contamination (open access)

Maximum Allowable Concentration for Air-Borne Beta Contamination

The following report discusses an equation derived by which the maximum allowable concentration in the atmosphere of a beta-omitting isotope for which lung damage is the limiting consideration can be calculated.
Date: July 5, 1951
Creator: Bailey, J. C. & Henry, H. F.
Object Type: Report
System: The UNT Digital Library