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Application of Photogrammetric Techniques for Environmental Surveillance of Amchitka Island, Alaska, Annual Progress Report, July 1, 1969 - June 30, 1970
Report concerning surveys made to determine the abundance and distribution of otters at Amchitka Island, Alaska, as well to document the effects of an underground nuclear reactor.
Date:
March 1972
Creator:
Stephan, Joachim G. & Mercier, Ian M.
System:
The UNT Digital Library
High-Level Radioactive Waste Management Alternatives Section 4: Geologic Disoposal
From foreword: "This report is a comprehensive overview study of potential alternative methods for long-term management of high-level radioactive waste...Disposal in terrestrial locations."
Date:
May 1974
Creator:
Schneider, K. J. & Platt, A. M.
System:
The UNT Digital Library
High-Level Radioactive Waste Management Alternatives Section 1: Summary, Section 2: Background and Data Base, Section 3: Evaluation Methodology
From foreword: "This report is a comprehensive overview study of potential alternative methods for long-term management of high-level radioactive waste."
Date:
May 1974
Creator:
Schneider, K. J. & Platt, A. M.
System:
The UNT Digital Library
A Sequence for Predicting Waste Transport by Ground Water
From introduction: "This paper describes a sequence for analyzing the effects of ground water flow on waste transport in natural soils."
Date:
April 15, 1965
Creator:
Nelson, R. William
System:
The UNT Digital Library
Geophysical Seismic Evaluation Study at Hanford
From introduction: "In June, 1963, a geophysical research program was conducted at Hanford to determine the feasibility and desirability of using seismic methods in geohydrologic studies. Detection and delineation were desired of seven different geological features that in some sites affect the movement of liquid radioactive wastes discharged to the ground."
Date:
December 1964
Creator:
Brown, Ruth E. & Raymond, John R.
System:
The UNT Digital Library
Static Tests of Corrosion Inhibitors for Aluminum and Carbon Steel
The experiments described in this report were performed for two purposes: (1) to find a chemical, or combination of chemicals, that would be effective for inhibiting corrosion of steel in static portions of the Hanford water systems, and (2) as screening tests to select candidate mixtures for further testing to replace sodium dichromate as the inhibitor of aluminum and steel corrosion in the Hanford single-pass reactor cooling water.
Date:
February 1965
Creator:
Richman, R. B.
System:
The UNT Digital Library
INDEX: a Computer Program for Indexing X-ray Diffraction Powder Patterns
From introduction: "...a logical system has been developed to yield rapidly the indexing of a given powder pattern by using an electronic computer."
Date:
January 1965
Creator:
Goebel, J. B. & Wilson, Archie Spencer
System:
The UNT Digital Library
PRTR second generation shim assembly
From introduction: "This document discusses the design, fabrication, assembly, and testing of a second generation shim rod assembly, and testing of a second generation shim rod assembly prototype for use in the Plutonium Recycle Test Reactor."
Date:
November 1964
Creator:
Rasmussen, D. E.
System:
The UNT Digital Library
The Recovery of Uranium from Chattanooga Shales
Recovery of uranium from Chattanooga shales.
Date:
January 14, 1954
Creator:
Wilson, R. Q.; Ewing, R. A.; Hanway, J. E., Jr.; Meeley, W. A.; Bearse, A. E.; Filbert, R. B., Jr. et al.
System:
The UNT Digital Library
Numerical Results for EGCR Moderator-Element Stress Problems
From introduction: "A recent report describes the development of a general program for the IBM Type 7090 electronic computer for calculating plane thermal stresses."
Date:
July 3, 1961
Creator:
Hulbert, Lewis E. & Redmond, Robert F.
System:
The UNT Digital Library
Hazards Summary Report for the Battelle Research Reactor
From summary: "This report was prepared for the Advisory Committee on Reactor Safeguards for their review and consideration of the potential hazards concerning the Battelle Memorial Institute Research Reactor."
Date:
April 4, 1955
Creator:
Chastain, J. W.; Redmond, R. F.; Klickman, A.; Anno, J. & Fawcett, S. L.
System:
The UNT Digital Library
Metallurgy Research Operation: Quarterly Progress Report, January - March 1965
Quarterly progress report on a project to test the radiation effects on metallurgy.
Date:
April 15, 1965
Creator:
Cadwell, J. J.; Bierlein, T. K.; Bement, A. L.; Dillon, R. L. & Wheeler, R. G.
System:
The UNT Digital Library
Fast Flux Test Facility Studies Progress Report: April 1965
From abstract: "...limited study work was performed on the conceptual design of the proposed fast flux test facility and information was obtained in important areas of supporting technology."
Date:
April 1965
Creator:
Astley, E. R.
System:
The UNT Digital Library
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
System:
The UNT Digital Library
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
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
Ceramic Investigations of UO₂
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.
System:
The UNT Digital Library
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-UO₂ 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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
A Study of Aluminum-Uranium Alloys
Report discussing the redetermination of liquids for aluminum alloys containing 13 to 25 w/o uranium by metallographic examination, thermal analyses, and electrical resistance measurements. In addition, phase diagrams and a method for producing sound, homogeneous aluminum 16 w/o uranium alloy sleeve castings are presented.
Date:
January 19, 1956
Creator:
Saller, Henry A.; Dickerson, Ronald F.; Rough, Frank A.; Foster, Ellis L.; Bauer, Arthur A. & Lulay, John R.
System:
The UNT Digital Library