A Continuous Water Monitor for Detecting PPM Quantities of Alkali Metals (open access)

A Continuous Water Monitor for Detecting PPM Quantities of Alkali Metals

Abstract: "This report describes a flame photometric system which continuously monitors a process water stream for ppm quantities of alkali metals, and automatically diverts the stream when the contamination exceeds a pre-determined level."
Date: June 20, 1955
Creator: Been, Julian F.
Object Type: Report
System: The UNT Digital Library
Potential Applications of Nuclear Energy for Process and Space Heat in the United States (open access)

Potential Applications of Nuclear Energy for Process and Space Heat in the United States

A survey and analysis of the potential opportunity for the use of nuclear reactors to satisfy process and space heat requirements in the continental United States and Alaska has been completed. The greatest emphasis has been devoted to manufacturing industries that utilize large quantities of process heat.
Date: October 1958
Creator: Geiringer, Paul Ludwig & Goodfriend, Morton J.
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
The Ductility of Brazed Stainless Steel Joints (open access)

The Ductility of Brazed Stainless Steel Joints

Abstract: "The ductility of Type 310 stainless steel T-joints brazed with GE-62 brazing alloy was measured at room temperatures 1200, 1650, and 1800 F. The measure of ductility was taken as the plastic axial strain required to crack braze fillets in T-section tensile specimens. At elevated temperatures, the ductility of as-brazed joints approximated that of the stainless steel, but at room temperature the brazed joints had only one-tenth the ductility of the base metal. Annealing for 16 hr at 1800 F in air was found to triple the room-temperature ductility of the brazed joint."
Date: July 8, 1953
Creator: Saller, Henry A.; Stacy, J. T. & Eddy, N. S.
Object Type: Report
System: The UNT Digital Library
The Effect of Copper, Nickel, Iron, and Chromium on the Tensile Properties of Preferentially Oriented Beryllium Sheet (open access)

The Effect of Copper, Nickel, Iron, and Chromium on the Tensile Properties of Preferentially Oriented Beryllium Sheet

From abstract: The planes and modes of fracture as a result of the mixture of beryllium and other elements were investigated.
Date: February 14, 1958
Creator: Yans, F. M.; Donaldson, A. D. & Kaufmann, A. R.
Object Type: Report
System: The UNT Digital Library
Extrusion Cladding of Fuel Element (open access)

Extrusion Cladding of Fuel Element

From introduction: "This investigation was undertaken with the general objective of determining whether uranium core could be sheathed with aluminum by an extrusion-cladding process. The ultimate objective of this work was to determine the feasibility of extrusion cladding flat plates of uranium."
Date: March 22, 1955
Creator: Slunder, C. J.; Fiorentino, R. J. & Hall, A. M.
Object Type: Report
System: The UNT Digital Library
Electroplated Metals on Uranium for Aluminum Cladding (open access)

Electroplated Metals on Uranium for Aluminum Cladding

Abstract: "Aluminum-clad nickel-plated uranium is corrosion resistant in boiling water. Samples with intentional defects in the aluminum-nickel clodding layers, after testing for more than 300 hr. showed no sign of rapid failure. The study of electroplated metals on uranium for aluminum cladding has defined the effects of several processing variables on the corrosion resistance. The quality of the uranium and the quality of the aluminum-nickel bond were important. Heat treatment and vacuum outgassing of the nickel-plated uranium prior to aluminum cladding were beneficial, and minimizing the amount of air present in the hot-press assembly was desirable. Variation in the steps for electroplating on uranium did not affect the corrosion resistance of aluminum-clad uranium."
Date: May 4, 1955
Creator: Beach, John G.; Schickner, William C.; Hopkinson, Dolores. & Faust, Charles L.
Object Type: Report
System: The UNT Digital Library
Ceramic Investigations of UOâ‚‚ (open access)

Ceramic Investigations of UOâ‚‚

This report covers the progress made on an intensive program to develop and evaluate UO2 as a possible fuel element for the PWR.
Date: June 16, 1955
Creator: Allison, Adrian G. & Duckworth, Winston H.
Object Type: Report
System: The UNT Digital Library
The Fabrication of Subassemblies for the Supercritical-Water Reactor (open access)

The Fabrication of Subassemblies for the Supercritical-Water Reactor

In studies of the fabrication of fuel subassemblies for the supercritical-water reactor, the limited ductility of stainless steel-UOâ‚‚ fuel sheet made the fabrication of corrugated-flat-plate-type subassemblies impractical. A fabricable MTR-type assembly, 5/8 in. square and 30 in. long, was developed. Methods for edge cladding fuel sheet were developed and a brazing alloy, GE-75, was found to be corrosion resistant in supercritical water.
Date: August 16, 1954
Creator: Keeler, J. R. & Hare, Alan W.
Object Type: Report
System: The UNT Digital Library
The Effects of Chemical Impurities on the Quality of Rolled Uranium Rod (open access)

The Effects of Chemical Impurities on the Quality of Rolled Uranium Rod

Abstract: "Thirty-four uranium ingots containing controlled amounts of carbon, nitrogen, and Mgl2 slag were cast, rolled, and examined to investigate the relation between these impurities and the quality of the rolled rod. Carbon in concentrations up to 1400 ppm and nitrogen up to 170 ppm, either singly or in combination, had no significant effect on the number of defects observed in the rolled rod. The quality of the rods, however decreased with increasing amount of slag necessary to cause observable differences in the rod could not be detected on analysis, but was visible in the microstructure."
Date: October 1, 1954
Creator: Saller, Henry A.; Keeler, J. R. & Cuddy, L. J.
Object Type: Report
System: The UNT Digital Library
The tensile strength of solid-state bonded aluminum and nickel-plated uranium (open access)

The tensile strength of solid-state bonded aluminum and nickel-plated uranium

A report intended to aid in the evaluation of solid-state bonding techniques for cladding natural-uranium fuel-element cores with aluminum, tensile specimens which are 1/4 in. in diameter and 3 in. long.
Date: 1954
Creator: Saller, Henry A.; Dickerson, R. F. & Carlson, R. J.
Object Type: Report
System: The UNT Digital Library
The Properties and Heat Treatment of Zirconium-Uranium Alloys (open access)

The Properties and Heat Treatment of Zirconium-Uranium Alloys

From Abstract: "The heat treatment and mechanical properties of four zirconium alloys...were investigated. Tensile, hardness, Jominy end-quench, and metallographic data constitute the basis for much of the report. Other data reported include the results of high-temperature creep, tensile, hardness, cold rolling, thermal-cycling, and dynamic-modulus tests." A connection is made between the behavior of these four alloys and more alloys in the zirconium-uranium system.
Date: January 10, 1955
Creator: Chubb, Walston; Muehlenkamp, G. T. & Manning, G. K.
Object Type: Report
System: The UNT Digital Library
Studies on Glass Dosimeters: Final Report for the Period July 1, 1954 Through June 30, 1955 (open access)

Studies on Glass Dosimeters: Final Report for the Period July 1, 1954 Through June 30, 1955

From introduction: There is a growing possibility that in the future certain foods, drugs, and biological materials may be treated by ionizing radiations on a production-line basis.
Date: 1955
Creator: Proctor, Bernard E.; Goldblith, Samuel A. & Davison, Sol
Object Type: Report
System: The UNT Digital Library
Uranium Migration in UOâ‚‚-Bearing Ceramics (open access)

Uranium Migration in UOâ‚‚-Bearing Ceramics

This report follows a preliminary study on uranium migration in pressed and sintered UO2-bearing bodies based on MoSi2 or Al2O3.
Date: September 4, 1953
Creator: Quirk, J. F.; Smalley, A. K.; Duckworth, W. H. & Ferrell, Edward Francis.
Object Type: Report
System: The UNT Digital Library
Design and Feasibility Study of a Pebble Bed Reactor-Steam Power Plant (open access)

Design and Feasibility Study of a Pebble Bed Reactor-Steam Power Plant

Originally issued as S and P 1963A, Parts I and II. This report covers a design and feasibility study of a pebble bed reactor-steam power plant of 125 megawatt electrical output. The reactor design which evolved from this study is a two-region thermal breeder, operating on the uranium-thorium cycle, in which all core structural materials are graphite. Fuel is in the form of unclad spherical elements of graphite, containing fissile and fertile material. The primary loop consists of the reactor plus three steam generators and blowers in parallel. Plant design and system analysis including cost analysis and capital cost summary are given.
Date: May 1, 1958
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Evaluation and Consolidation of Electrolytic Thorium (open access)

Evaluation and Consolidation of Electrolytic Thorium

Abstract: "Sound, fabricable ingots of thorium were produced by triple are melting of electrolytic thorium. Consumable electrodes were fabricated by tack welding of cold-pressed and vacuum-sintered bars of the granular thorium electrodeposited from a molten-salt bath. The hydrogen content of the electrodeposited material was reduced from 80 to 4 ppm by vacuum sintering at 1250 C at pressures below 1 x 10-(-3) mm of mercury. Both sodium and chlorine content were reduced during melting; sodium from 250 to 25 ppm and chlorine from 1000 to 30 ppm. Oxygen and HCl acid-insoluble contents increased during sintering and melting. Oxygen content increased from 0.35 to 0.50 w/o and HCl acid-insoluble content from 0.8 to 4.0 w/o. A starlike includion revealed by metallographic examination of the as-cast thorium was identified as ThO2."
Date: June 15, 1955
Creator: Saller, Henry A.; Dickerson, Ronald F. & Foster, Ellis L.
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
Further Studies on Large-Batch Melting of Uranium (open access)

Further Studies on Large-Batch Melting of Uranium

The following report focuses on an investigation made to determine if vacuum melting was an absolutely necessary step in the metallurgical process of melting and casting uranium.
Date: July 11, 1955
Creator: Rengstorff, George W. & Lownie, Harold W., Jr.
Object Type: Report
System: The UNT Digital Library
Metallurgy Division Quarterly Progress Report: Period Ending October 31, 1951 (open access)

Metallurgy Division Quarterly Progress Report: Period Ending October 31, 1951

This quarterly progress report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses thorium research, the mechanical properties of metals including thorium, uranium, inconel, and z-nickel, the ANP program (including the following topics: the physical chemistry of liquid metals, and welding research), and the materials testing reactor program.
Date: April 21, 1952
Creator: Frye, John H., Jr., 1908-2001 & Bridges, W. H.
Object Type: Report
System: The UNT Digital Library
Chemistry Division Quarterly Progress Report: Period Ending September 30, 1951 (open access)

Chemistry Division Quarterly Progress Report: Period Ending September 30, 1951

This quarterly progress report discusses topics of research and experimentation at the Oak Ridge National Laboratory, including inorganic chemistry, nuclear chemistry, radio-organic chemistry, chemistry of separations processes, chemical physics, radiation chemistry, chemistry of the solid state, instrumentation, reactor chemistry.
Date: September 30, 1951
Creator: Lind, Samuel C., (Samuel Colville), 1879-1965; Boyd, G. E. & Bredig, M. A.
Object Type: Report
System: The UNT Digital Library
Aircraft Nuclear Propulsion Project Quarterly Progress Report: Period Ending September 10, 1951 (open access)

Aircraft Nuclear Propulsion Project Quarterly Progress Report: Period Ending September 10, 1951

The first part of this quarterly progress report details reactor theory and design, discussing the aircraft reactor experiment, experimental reactor engineering, reactor physics, and critical experiments. The second part of this report is not included. The third part of this quarterly progress report details materials research, discussing corrosion research, physical properties and heat-transfer research, metallurgy and ceramics, chemistry of high-temperature liquids, and radiation damage. The fourth part of this quarterly progress report details alternate systems, discussing a supercritical water reactor, circulating-moderator-coolant reactors. The fifth part of this quarterly progress report includes appendixes.
Date: January 9, 1952
Creator: Briant, R. C.; Ellis, C. B. & Cottrell, William B.
Object Type: Report
System: The UNT Digital Library
Measurement of the Behavior of a Plasma in a Magnetic Field by Means of Probes (open access)

Measurement of the Behavior of a Plasma in a Magnetic Field by Means of Probes

Abstract: "Probes were used to measure certain properties of the cloud of positive ions and electrons ejected from a pulsed ion source having two hydrogen-loaded electrodes. Time-of-flight measurements show: the presence of H+ ions with 50 ev directed energy; an increase of this energy with increasing pulse current in the source; a higher peak yield of ions with higher peak currents in the source; and higher yields and higher ion energies up to 110 ev have been recorded with the use of a pulsed magnetic field impressed upon the source. The neutral positive ion-electron beam from the source has been projected against an increasing magnetic field and the reflected and transmitted signals have been recorded and compared as a function of the magnetic field. Probe signals from the plasma as it encounters the magnetic field are oscillatory, suggesting that magnetohydrodynamic phenomena are presented."
Date: December 1, 1954
Creator: Bostick, W. H.; Zizzo, S. G. & Cook, Buford
Object Type: Report
System: The UNT Digital Library
Use of Thermal Electromotive Forces to Product Magnetic Field in a Controlled Thermonuclear Reactor (open access)

Use of Thermal Electromotive Forces to Product Magnetic Field in a Controlled Thermonuclear Reactor

The following report investigates the possible use of thermal emf's to produce the plasma-containing magnetic field in a thermonuclear reactor.
Date: December 27, 1954
Creator: Northrop, Theodore G.
Object Type: Report
System: The UNT Digital Library