Brief Review of Heat Transfer Problems Encountered in the Production of Magnetic Fields (open access)

Brief Review of Heat Transfer Problems Encountered in the Production of Magnetic Fields

The design of internally cooled electrical coils for the production of high frequency intensity magnetic fields presents many new aspects and combinations of the familiar modes of heat transfer. However, the customary methodology appears to be sufficient for preliminary analysis and understanding of those problems. This methodology comprises the derivation of a qualitative, approximate equation expressing the relative performance of the various parts of a system, followed by an examination of this equation in order to locate the limiting features of the system. These features are then investigated by more powerful methods, which in turn provide guidance for development research in the laboratory.
Date: May 25, 1959
Creator: Alexander, L. G.
Object Type: Report
System: The UNT Digital Library
Steady-State Recirculated Reactor Stability and Operational Characteristics - Water and Metal Temperature Coefficients (open access)

Steady-State Recirculated Reactor Stability and Operational Characteristics - Water and Metal Temperature Coefficients

It is desirable that a reactor exhibit a self-regulating effect. If this were not true any disturbance to the reactor would result in a continual increase in the magnitude of the disturbance and the reactor would be unstable. In this investigation the reactor is considered to have two reactivity feed-backs: metal temperature and water temperature reactivity effects. These two variables through a metal temperature coefficient and water temperature coefficient determine not only the reactor stability but also determine many operational characteristics.
Date: December 23, 1959
Creator: Allen, C. W.
Object Type: Report
System: The UNT Digital Library
Possible Test Sites in Granitic Rocks in the United States (open access)

Possible Test Sites in Granitic Rocks in the United States

Introduction: This report describes areas of granitic rocks suitable for underground nuclear tests within Federally-controlled land in the continental limits of the United States. This information was requested of the U. S. Geological Survey by the Albuquerque Operations Office of the U. S. Atomic Energy Commission, and was compiled during March 1959 by D. C. Alvord, W. J. Carr, P. M. Hanshaw, S. P. Kanizay, C. S. Robinson, R. W. Schnabel, J. A. Sharps, and C. T. Wrucke.
Date: July 1959
Creator: Alvord, Donald C.; Carr, Wilfred James; Hanshaw, Penelope M.; Kanizay, Stephen P.; Robinson, Charles Sherwood; Schnabel, Robert W. et al.
Object Type: Report
System: The UNT Digital Library
Physical Properties of Neutralized Zirflex Waste (open access)

Physical Properties of Neutralized Zirflex Waste

Zirflex cladding waste is to be neutralized to pH 10 before transfer to waste storage tanks. This treatment causes the precipitation of zirconium oxide or hydroxide, which may lead to flow difficulties during transfer. The purpose of this investigation was to determine the physical properties and flow characteristics of the neutralized slurry to assist in the selectin of satisfactory transfer equipment and storage conditions.
Date: June 8, 1959
Creator: Amos, L. C.
Object Type: Report
System: The UNT Digital Library
Fuels Preparation Department Analytical Laboratory Manual (open access)

Fuels Preparation Department Analytical Laboratory Manual

The purpose of the Analytical Laboratory Manual is to assemble the basic procedures to be used for the analyses of materials employed within the Fuels Preparation Department. The methods appear in detailed steps suitable for laboratory use. This document replaces the "Essential Material Analytical Manual, " HW-25375 and "Metal Preparation Analytical Manual," HW-30862.
Date: June 1959
Creator: Analytical Laboratory Manufacturing Operation
Object Type: Report
System: The UNT Digital Library
Comments on Equipment for a PRTR Water Quality Control Laboratory (open access)

Comments on Equipment for a PRTR Water Quality Control Laboratory

This document describes required laboratory space and lists major equipment items necessary for a routine water quality laboratory in the P. R. T. R. Building. During discussions with R. D. Widrig and V. L. Rooney about the analytical sample program for the Plutonium Recycle Test Reactor, the author was asked to summarize equipment and space needs for a water control laboratory to provide routine analytical coverage on some of the water systems. Based upon 1706-KE-KER experience, some operating personnel may be used to provide analytical coverage on those routine analyses that are needed on around-the-clock basis with a savings of both time and money.
Date: December 1, 1959
Creator: Anderson, H. J. & Peray, R. E.
Object Type: Report
System: The UNT Digital Library
The Injection Casting of Plutonium (open access)

The Injection Casting of Plutonium

Plutonium metal can be injected into cold metal molds to form castings with thin walls. The operation is performed in a vacuum chamber, using an inert gas as the injecting medium. Sound pieces free of gas cavities can be made using either pure or delta-stabilized plutonium. This report describes the equipment and techniques used to cast a typical thin section piece in the form of a 6 in. diameter, 45' cone.
Date: January 1959
Creator: Anderson, J. W.
Object Type: Report
System: The UNT Digital Library
Neutron-Flux Measurements in a Concentric-Cylinder Fuel Element (open access)

Neutron-Flux Measurements in a Concentric-Cylinder Fuel Element

The following report presents neutron-flux measurements made with a concentric-cylinder element (Mark II) and includes axial, radial, and peripheral flux distributions.
Date: January 29, 1959
Creator: Anno, James N.; Fairand, Barry P. & Chastain, Joel W., Jr.
Object Type: Report
System: The UNT Digital Library
Operating Manual for the Argonaut Reactor (open access)

Operating Manual for the Argonaut Reactor

The design of the Argonaut (Argonne Nuclear Assembly for University Training) was initiated by the Reactor Engineering Division of Argonne National Laboratory to satisfy needs for a low-power reactor facility within the Laboratory, and for training uses within the international School of Nuclear Science and Engineering (ISNSE). It was intended primarily for instruction and research in reactor physics. It was also considered as a possibility that it would fulfill the requirements of universities engaged in a program of nuclear science. The cost of the facility was to be kept to a minimum consistent with the high degree of inherent safety and a great amount of flexibility in the system. The basic design stemmed from the Knolls Atomic Power Laboratory Thermal Test Reactor* (TTR), now called Nuclear Test Reactor (NTR). Modification during the course of the work justified the new name "Argonaut".
Date: August 1959
Creator: Argonne National Laboratory
Object Type: Report
System: The UNT Digital Library
Radiation Hazards from Recycled Reactor Fuel (open access)

Radiation Hazards from Recycled Reactor Fuel

The radiation hazards associated with recycled nuclear reactor fuels will greatly complicate the handling and refabrication of these fuels. This problem is most serious with U-233 and plutonium fuels where the presence of U-232 and the heavier isotopes of plutonium contribute energetic alpha, gamma, and neutron radiations at levels many times that from isotopically pure U-233 and Pu-239. This report summarizes present knowledge of the radiation hazards associated with recycled fuel and the additional data needed to make a thorough evaluation of these hazards.
Date: June 9, 1959
Creator: Arnold, E. D.
Object Type: Report
System: The UNT Digital Library
Problems in Accountability Measurements Associated with the Interim Chemical Processing Program (open access)

Problems in Accountability Measurements Associated with the Interim Chemical Processing Program

Available knowledge of precision limits in S.S. accountability measurements and/or calculations by reactor and chemical processing groups is surveyed and summarizes. Experience in comparisons of reactor (production and research) calculations versus chemical plant accountability measurements is also reported. A general tentative conclusion is that available precisions (+/- 0.54 to +/- 0.78% ) in chemical plant measurements is also reported. A general tentative conclusion is that available precisions (+/- 1.0 to +/- 11.0%) possible by calculations (nuclear and/or engineering) of power reactor systems; however, with operation and empirical experience (e.g. less than +/-1.0%
Date: May 28, 1959
Creator: Arnold, E. D. & Gresky, A. T.
Object Type: Report
System: The UNT Digital Library
Drumlins and Related Streamline Features in the Warwick-Tokio Area, North Dakota (open access)

Drumlins and Related Streamline Features in the Warwick-Tokio Area, North Dakota

Report discussing the northeast-trending drumlins and related streamline features of late Pleistocene age found in the Warwick-Tokio area of the Devils Lake region of North Dakota.
Date: 1959-04~
Creator: Aronow, Saul
Object Type: Paper
System: The Portal to Texas History
Bibliography of Published Papers of the Atomic Bomb Casualty Commission (1947-1959) (open access)

Bibliography of Published Papers of the Atomic Bomb Casualty Commission (1947-1959)

References to 193 publications of staff members of the Atomic Bomb Casualty Commission during 1947 through 1959 are listed in both English and Japanese. Author and subject indexes are included.
Date: 1959
Creator: Atomic Bomb Casualty Commission
Object Type: Report
System: The UNT Digital Library
Evaluation of a California Bentonitic Clay for Use in Oil-Well Drilling Muds (open access)

Evaluation of a California Bentonitic Clay for Use in Oil-Well Drilling Muds

Report issued by the Bureau of Mines over studies conducted on the bentonite deposits of San Benito County, California. As stated in the introduction, "the purpose of the study was to learn if these large deposits contain bentonite of sufficient quality and quantity to be of economic value as an oil-well drilling mud additive" (p. 1). This report includes tables, maps, illustrations, and photographs.
Date: 1959
Creator: Aune, Quinton A.; Caraway, W. Hodge; Morris, Frank C. & Gates, George Laurence
Object Type: Report
System: The UNT Digital Library
Development of Ribbed Jacket Tubing for PTRT (open access)

Development of Ribbed Jacket Tubing for PTRT

One of the UO2 fuel element designs proposed for use in the PTRT is the nested tubular concepts. This configuration compromises a central fuel todo surrounded by two concentric tubes of fuel (see sketch, appenx I.) . These UO2 shapes are to be jacketed in the Zircaloy and must be separated from each other and the procuresses tyvm vt annular spaces for the passage of coolant. The annuli are established and and maintained by the longitudinal ribs on the outer surface of all three jacketed fuel elements.
Date: September 4, 1959
Creator: Aungst, R. C.
Object Type: Report
System: The UNT Digital Library
N. S. Savannah Fuel Design and Development Program: Fuel Rod Vibration (Preliminary Report) (open access)

N. S. Savannah Fuel Design and Development Program: Fuel Rod Vibration (Preliminary Report)

This is a preliminary report on the investigation of the N.S. Savannah replacement fuel rod vibration amplitude when excited by water flowing parallel to the axis of the fuel rod. Methods of calculating the fuel rod frequency in air were verified by experiment. Work is continuing to establish the validity of methods of calculating natural frequencies in water and to confirm the correlation of flow induced vibration amplitude found in reference (1).
Date: September 25, 1959
Creator: Bailey, J. A. & Shields, C. M.
Object Type: Report
System: The UNT Digital Library
Suggested Major Equipment for NPR Water Quality Control Labs (open access)

Suggested Major Equipment for NPR Water Quality Control Labs

Two water quality control labs are being provided for the the NPR. One, a "cold" lab, is located in the183 Building adjacent to the control room. Its primary purpose is to provide facilities for quality control of the output of the filter plant and the demineralizer plant. The other, a "hot" lab, is located in the 190 Building. Its primary purpose is to provide facilities for the quality control of the primary and secondary coolants, and the moderator coolant.
Date: July 30, 1959
Creator: Bainard, W. D.
Object Type: Report
System: The UNT Digital Library
Experimental Program for the PRTR Gas Loop (open access)

Experimental Program for the PRTR Gas Loop

Early in the U.S. gas-cooled reactor program, it was recognized that a considerable research and development effort would be needed to utilize the full potential of gas cooling. Hanford Laboratories contribution to this program began in August, 1958 when a graphite studies program was initiated. The primary objectives of the Hanford program are: (1) to secure improved knowledge of the reaction of gas coolants with protected and unprotected graphites over a range of conditions of practical interest for gas cooled power reactors with tolerable damage to the graphite moderator.
Date: September 1, 1959
Creator: Baker, D. E.
Object Type: Report
System: The UNT Digital Library
Further Corrosion Tests on Materials in Regenerative Air Preheaters (open access)

Further Corrosion Tests on Materials in Regenerative Air Preheaters

Report issued by the Bureau of Mines over tests conducted on regenerative air preheaters. The corrosion rates of different materials are presented. This report includes tables, graphs, illustrations, and photographs.
Date: 1959
Creator: Barkley, J. F.; Karlsson, Hilmer & Stark, C. F.
Object Type: Report
System: The UNT Digital Library
Present Status of Semiconductor Particle Counters (open access)

Present Status of Semiconductor Particle Counters

This review lists some of the salient features of semiconductor particle counters and cannot claim to contain an exhaustive listing of all the work in the field. Performance results on the surface-barrier counters as developed at California Institute of Technology are included as typical for this type of counter, though comparable results have been obtained elsewhere.
Date: November 23, 1959
Creator: Barnes, C. A.
Object Type: Report
System: The UNT Digital Library
Geology and Coal Resources of the Homer District, Kenai Coal Field, Alaska (open access)

Geology and Coal Resources of the Homer District, Kenai Coal Field, Alaska

From abstract: The Homer district of the Kenai coal field is about 100 miles southwest of Anchorage, in south-central Alaska. It covers an area of about 1,100 square miles on the west side of the Kenai Peninsula, between Tustumena Lake and Kachemak Bay. The principal settlement is Homer, at the southern end of the district, which is connected by the gravel-surfaced Sterling Highway with the Alaska highway system and The Alaska Railroad, and is also served by ocean transportation and one airline.
Date: 1959
Creator: Barnes, Farrell F. & Cobb, Edward H.
Object Type: Report
System: The UNT Digital Library
Geology and Coal Resources of the Little Susitna District, Matanuska Coal Field, Alaska (open access)

Geology and Coal Resources of the Little Susitna District, Matanuska Coal Field, Alaska

From introduction: This report is based on preliminary surface mapping in the summer of 1952 and on subsurface exploration with a bulldozer powerauger unit in the summers of 1953 and 1954. In 1952 F. F. Barnes was assisted by Alfred Oestreich, geologist, and Lewis Ladwig and Richard Pack, field assistants. From July 2 to August 31, 1953, F. F. Barnes and Daniel Sokol were assisted by W.T. Ashlock and R. E. Rowland, field assistants, and by a bulldozer operator-mechanic. From June 23 to July 27, 1954, Barnes and Sokol were assisted by A. E. Burford and W. S. Hopkins, geologists, and an operator-mechanic.
Date: 1959
Creator: Barnes, Farrell F. & Sokol, Daniel
Object Type: Report
System: The UNT Digital Library

[Illustrations: Figures 1-10]

Maps and charts illustrating aspects of a photogeologic reconnaissance study of the spatial relationship of uranium deposits to structure and stratigraphy in Duval County, Texas.
Date: February 1959
Creator: Barnes, John C.
Object Type: Dataset
System: The UNT Digital Library
Study of Dispersant Agents for Thorium Oxide (open access)

Study of Dispersant Agents for Thorium Oxide

A preliminary study of dispersing agents for thorium oxide has been completed and several of the dispersants have possible uses. Also many of the industrial dispersing agents tested are not usable with thorium oxide due to induced behavior causing balling and caking. The effects of nitric acid concentration have been observed to also effect each dispersing agent.
Date: August 7, 1959
Creator: Bate, L. C. & Leddicotte, G. W.
Object Type: Report
System: The UNT Digital Library