Resource Type
Serial/Series Title
Atomic Energy Commission Reports
311
NACA Research Memorandums
115
AEC research and development report
89
Hanford Works Reports
71
HW (Series)
58
NACA Technical Reports
46
North American Aviation Reports
45
Health and Safety Laboratory Reports
42
General Electric Company Atomic Power Reports
41
TID
41
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731 Matching Results
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Report on Hack's Canyon Uranium Mine, Mohave County, Arizona
This is a geological report on the uranium mine in Hack's Canyon, Mohave County, Arizona.
Date:
September 1, 1948
Creator:
Dunning, Charles H.
Object Type:
Report
System:
The UNT Digital Library
Uranium in Peru
Introduction: From the inception of the effort to utilize atomic energy Perú has been of interest as a possible source of radioactive raw materials because of its great variety and abundance of metals. Because of this and a desire at that time to develop additional supplies of uranium, a cooperative program to search for uranium deposits was initiated in 1953 by the Junta and the USAEC.
Date:
January 1, 1962
Creator:
Gabelman, John W. & Beard, Raymond R.
Object Type:
Report
System:
The UNT Digital Library
Radial distribution of plasma in Astron's E-layer
A report discussing a more general analysis of "the relation between plasma pressure in the Astron [Thermonuclear Reactor] and the magnetic field of the E-layer" which is described in UCRL-5032. The analysis given in this report has "no restriction to the exponential form and [satisfies] the condition that the pressure at the axis shall be zero."
Date:
December 1, 1958
Creator:
Tonks, Lewi, 1897-1971
Object Type:
Report
System:
The UNT Digital Library
Uranium in the Southern United States
From introduction: The purpose of this study was to compile information on and systematically assess uranium and other radioactive occurrences in the region.
Date:
July 1, 1969
Creator:
Southern Interstate Nuclear Board
Object Type:
Report
System:
The UNT Digital Library
The High Intensity Food Irradiator: Report 17
From introduction: A thorough investigation, both experimental and theoretical was carried out on plaque type radiators. Five phases of the work are reported: preliminary design analysis, experimental measurements, computational program and analytical studies, followed by a general discussion of source design principles. The results are summarized in graphs and formulae which may be applied to other design requirements.
Date:
May 1, 1960
Creator:
Curtiss-Wright Corporation
Object Type:
Report
System:
The UNT Digital Library
A Reversing Logarithmic DC Amplifier
Purpose: Automatic recording equipment was designed for use with a high temperature Sykes experiment in which calorimetric measurements were to be made to temperatures approaching 2000* C. At such high temperatures, radiation becomes the dominant mechanism for heat transfer. The temperature differences which are used to determine the magnitude of this transfer no longer are directly proportional to it, but must be related by the Stefan-Boltzman law of radiation.
Date:
January 1, 1954
Creator:
Carter, R. L.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Irradiated OMRE Fuel Elements First Core Loading
Abstract: Irradiated fuel elements from the Organic Moderated Reactor Experiment (OMRE) first core loading have been examined and evaluated to determine: (1) the stability of the floating plate fuel element design, (2) the stability of the stainless steel clad UO2 - stainless steel cermet core fuel plates under irradiation and exposure to the organic coolant, (3) the extent and nature of deposits on the fuel element services, and (4) the distribution of burnup in the fuel elements.
Date:
March 1, 1960
Creator:
Walter, J. H.; Leirich, J. F. & Calkins, G. D.
Object Type:
Report
System:
The UNT Digital Library
Remote Maintenance Techniques for the Processing Refabrication Experiment
Abstract: This report outlines the general techniques developed for replacement of PRE in-cell equipment or equipment components.
Date:
December 1, 1958
Creator:
Stoker, Donald J.
Object Type:
Report
System:
The UNT Digital Library
Organic Moderated Reactor Experiment : Safeguards Summary
Abstract: This report presents a description of the Organic Moderated Reactor Experiment (OMRE), of the hazards associated with this experiment, and all of the safeguards taken to ensure the safety of the operating personnel and the population of the surrounding area.
Date:
February 1, 1958
Creator:
Sletten, H. L. & Blue, L. R.
Object Type:
Report
System:
The UNT Digital Library
Preliminary Test of Natural-Circulation Double-Tube Steam Generator
Abstract: Testing of the Natural Circulation Steam Generator has been conducted with the Sodium Reactor Experiment. A necessary modification of the original feed-water control system was utilized.
Date:
December 1, 1959
Creator:
Welsh, R. D.
Object Type:
Report
System:
The UNT Digital Library
OMR Degasifier Loop Experiment
Abstract: A loop has been constructed to study the removal of water and highly volatile materials from Organic Moderated Reactor coolant by vacuum degasification. An analysis of the process was made to determine the most important parameters for study during the experimental program.
Date:
May 1, 1960
Creator:
Corporales, G. W. & Benson, P. R.
Object Type:
Report
System:
The UNT Digital Library
OMRE Fuel Plate Surface Temperature Measurement
Abstract: Accurate measurement of OMRE fuel-element surface temperatures is important for evaluation of the performance of organic compound as moderator and coolant materials in nuclear reactors; a mixture of polyphenyls has been used in reactor operation to-date.
Date:
May 1, 1960
Creator:
Sudar, S.
Object Type:
Report
System:
The UNT Digital Library
Plutonium: Enriched OMR Cores
Abstract: The influence of plutonium on the nuclear characteristics of organic moderated cores is studied.
Date:
May 1, 1960
Creator:
Connolly, T. J.
Object Type:
Report
System:
The UNT Digital Library
Engineering Evaluation of a Mixed Alloy Fuel Element Irradiated at Elevated Temperatures in the SRE
Abstract: A fuel material evaluation was made by destructively examining a full-scale experimental fuel element, irradiated in the SRE to a maximum of 850 Mwd/MTU.
Date:
June 1, 1960
Creator:
Ballif, J. L.; Hayward, B. R. & Walter, J. W.
Object Type:
Report
System:
The UNT Digital Library
Mineralogy of Uranium-Bearing Deposits in the Boulder Batholith, Montana, Annual Report: April 1, 1953-March 31, 1954
Introduction: During the year 1952-1953, research on the Boulder batholith program was largely devoted to basic mineralogy studies of the "siliceous reef" and, to the extent possible at that time, the "base metal" deposits.
Date:
April 1, 1954
Creator:
Wright, Harold D.; Bieler, B. H.; Shulhof, W. P. & Emerson, D. O.
Object Type:
Report
System:
The UNT Digital Library
Current Beryllium Literature : A Selected Bibliography, August 1959 - December 1969
"This bibliography lists selected books, articles, and unclassified reports which have appeared in the following abstracts and indexes between August 1959 and December 1960."
Date:
May 1, 1961
Creator:
Lane, Zanier D.
Object Type:
Report
System:
The UNT Digital Library
Hydrogeochemical and Stream-Sediment Survey (NURE): Preliminary Report on the Walker River Basin Study (California/Nevada)
From introduction: The objective of this survey is to develop a geochemical data base for use by the private sector to locate regions of anomalous uranium content. Prior to wide area coverage, several pilot studies are being undertaken to develop and evaluate sampling and analytical techniques. The first of these studies was conducted in the Walker River Basin.
Date:
July 1, 1976
Creator:
Lawrence Livermore Laboratory
Object Type:
Report
System:
The UNT Digital Library
A General Purpose Log Counting Rate Meter Model B
Abstract: This report is a brief description of a general purpose logarithmic counting rate meter developed at the Knolls Atomic Power Laboratory. The theory of operation and the circuit design are discussed. The use of a diode as a logarithmic element in the integrating circuit allows extremely accurate counting rate determinations over a five decade range.
Date:
November 1, 1954
Creator:
Stone, R. S. & Wade, E. J.
Object Type:
Report
System:
The UNT Digital Library
OMRE Fuel Removal and Shipping Equipment
Abstract: A portable assembly for handling and shipping OMRE fuel elements is described and details of its operation are given. Problems of heat transfer and radiation shielding are discussed, and detailed analysis are presented.
Date:
April 1, 1960
Creator:
Mallon, P. J.; Duncan, D. S. & Noyes, R. C.
Object Type:
Report
System:
The UNT Digital Library
Final Safeguards Summary Report for the Piqua Nuclear Power Facility
Summary: This report contains a description of the final design of the Piqua Nuclear Power Facility (PNPF); an outline of the test and operating procedures, and the organization and responsibilities; and a summary of the hazards and safeguards analyses that have been conducted to evaluate the safety of the facility operations.
Date:
August 1, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Thermal Cycling and Leakage Tests of 12-inch Valves for Sodium Service
Abstract: Tests were performed to determine the effect of thermal cycling on the across-the-seat leakage characteristics of commercially available valves considered for use in the sodium coolant system of the Hallam Nuclear Power Facility.
Date:
May 1, 1960
Creator:
Baroczy, C. J.
Object Type:
Report
System:
The UNT Digital Library
300,000-KWE SGR Nuclear Power Plant of Current Technology
Abstract: This report describes a 300,000-kwe, sodium-cooled, graphite-moderated nuclear power plant based on existing technical information.
Date:
August 1, 1960
Creator:
Renard, J.; Peckinpaugh, C. L. & Aronstein, R. E.
Object Type:
Report
System:
The UNT Digital Library
UC Fuel Element Design and Fabrication
Abstract: Uranium monocarbide shows considerable potential for use as a fuel in high temperature, high power density, nuclear power reactors. As Atomics International is proposing its use in sodium graphite type reactors, it was necessary to develop a process for fabricaing sodium bonded uranium carbide fuel elements.
Date:
August 1, 1964
Creator:
Draganchuk, W.
Object Type:
Report
System:
The UNT Digital Library
Study of SCTI Control System
Introduction: This report has been prepared to document the extensive analytical work required to design the control system for the Sodium Components Test Installation (SCTI), constructed for the Atomic Energy Commission at the Atomics International field laboratory.
Date:
December 1, 1964
Creator:
Griffin, C. W.
Object Type:
Report
System:
The UNT Digital Library