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Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 2. Plant Conceptual Studies
Second part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. II-i).
Date:
March 1962
Creator:
Combustion Engineering, inc. Nuclear Division.
Object Type:
Report
System:
The UNT Digital Library
Automatic Mass Spectrometer for Isotopic Analysis of Lithium
Report discussing an improvement program on lithium mass spectrometers.
Date:
March 15, 1962
Creator:
McBryde, W. T. & Gammon, E. F.
Object Type:
Report
System:
The UNT Digital Library
The Cold Pressing of Sinterable UO₂
The intent of this work was to explore more fully the pressing of sinterable UO2 powders into cylindrical compacts in the hope that a more precise prediction of green density in terms of powder properties, pressure, and geometry could be evolved.
Date:
March 27, 1961
Creator:
Levey, R. P., Jr.
Object Type:
Report
System:
The UNT Digital Library
A Nuclear Reactor System for Generating Power and Supplying Steam to a Water Desalination Plant in the Florida Keys
From foreword: The results of an engineering study directed toward the evaluation and selection of a nuclear reactor system designed to produce electricity and furnish steam to a water desalination plant in the Florida Keys are given in this report.
Date:
March 1964
Creator:
Burns and Roe
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Final Report: Investigation of Boiling Flow Regimes and Critical Heat Flux
From abstract: A program to investigate the mechanism of the critical heat flux condition from the standpoint of flow regimes has been initiated at Dynatech for the AEC. This report covers the work done on this investigation in the first year.
Date:
March 1, 1965
Creator:
Suo, M.; Bergles, Arthur E.; Doyle, Edward F.; Clawson, L. & Goldberg, P.
Object Type:
Report
System:
The UNT Digital Library
An Experimental Gamma Irradiator for Hospital Sterilization
From foreword: This report presents the preliminary design of a gamma irradiator intended for use as an experimental hospital sterilizer.
Date:
March 7, 1960
Creator:
Frankfort, J. Harry; Haram, S. & Wallach, S.
Object Type:
Report
System:
The UNT Digital Library
Transient Temperature Variations During the Self-Heating of a Plasma by Thermonuclear Reactions
Abstract: "The possibility of transient temperature variations during the self-heating of a plasma by thermonuclear reactions was investigated. Calculations were performed on an IBM Card Program Calculator. Estimates of the time scale for self-heating were obtained. It was concluded that it would be unsafe to assume that the nuclear temperature is always equal to or greater than the electron temperature in a discussion of plasma instabilities for a plasma with 10 percent or greater tritium concentration."
Date:
March 21, 1955
Creator:
Greyber, Howard D.
Object Type:
Report
System:
The UNT Digital Library
Magnetic Acceleration of a Plasma by a Rail Source
Abstract: "Two parallel wires close together with an arc between them form a hairpin-type of current configuration which should magnetically propel the plasma of the arc. By the time-of-flight measurements with probes it has been demonstrated that directed translational energies of 290 ev can be imparted to deuterons in a plasma produced by a high-current pulsed arc at the tips of two titanium wires loaded with deuterium. It is believed that three deuterons are actually magnetically propelled."
Date:
March 18, 1955
Creator:
Bostick, Winston H.
Object Type:
Report
System:
The UNT Digital Library
Initial Measurements on the Angular Distribution of Deuterium Plasma Produced by a Pulsed Spark Source
Abstract: "The deuterium plasma which is ejected by a 6000-ampere pulsed current through a rail-type spark source has a yield in the forward direction which is a factor of 5 to 10 greater than that in the perpendicular direction. This effect is believed to be due to the magnetic propulsion of the plasma."
Date:
March 24, 1955
Creator:
Bostick, W. H.
Object Type:
Report
System:
The UNT Digital Library
An Ultrasonic System for Testing Isotope Heat Capsules
Introduction: This report describes a program to develop a nondestructive (ultrasonic) tester and testing procedure to perform integrity tests on isotope heat source containers. The increased application of isotope heat sources has brought more attention to the engineering problems encountered during fabrication. One of the most important of these problems is insuring the isotope containment during the long unattended periods of use. To determine the integrity of the heat source container, a nondestructive testing procedure must be adopted to test each heat source after fabrication.
Date:
March 1968
Creator:
Dozer, B. E.
Object Type:
Report
System:
The UNT Digital Library
Pacific Northwest Laboratory Monthly Activities Report, Division of Biology and Medicine Programs: February 1967
Areas of work reported include: general radiation effects; toxicity of radioelements; combating detrimental effects of radiation; studies at the molecular and cellular level; environmental radiation studies; atmospheric radioactivity and fallout; marine sciences; radiological and health physics; and radiation instruments.
Date:
March 1, 1967
Creator:
Fawcett, S. 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
An Advanced Sodium-Graphite Reactor Nuclear Power Plant
Abstract: This report describes an advanced sodium-cooled, graphite-moderated nuclear power plant which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency.
Date:
March 15, 1960
Creator:
Churchill, J. R. & Renard, J.
Object Type:
Report
System:
The UNT Digital Library
The Effects of Irradiation Cycling on Pressurized Water Reactor Blanket Fuel Elements
From introduction: This report details the results of the post-irradiation examination of a test involving one defected rod and one undefected rod.
Date:
March 13, 1957
Creator:
Eichenberg, John D.
Object Type:
Report
System:
The UNT Digital Library
Thermal Cycling Tests of Porous Uranium
Abstract: It has been proposed that a fuel element containing porous uranium be used for moderately high temperature applications. In an effort to determine the structural integrity of this type of fuel body, thermal cycling tests have been conducted on porous uranium.
Date:
March 15, 1960
Creator:
Wilkinson, L. E.
Object Type:
Report
System:
The UNT Digital Library
Pacific Northwest Laboratory Monthly Activities Report, Division of Biology and Medicine Programs: February 1969
Progress is updated for projects related mostly to biological and ecological radiation effects.
Date:
March 1, 1969
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Development of High-Temperature Electrical Ground Test Heaters for the SNAP 10A Program
Introduction: The development and qualification of the system acceptance test heaters and the reactor simulator heater are described in this progress report.
Date:
March 1, 1965
Creator:
Blevitt, R.; Paine, G. & Sudar, S.
Object Type:
Report
System:
The UNT Digital Library
KEWB Program Quarterly Progress Report: July-September 1956
From abstract: The response of the reactor to forced oscillations has been investigated with the pile oscillator technique and the data are presently being analyzed.
Date:
March 1, 1957
Creator:
North American Aviation. Atomics International Division. Kinetic Experiments on Water Boilers Program.
Object Type:
Report
System:
The UNT Digital Library
Organic Moderated Reactor Experiment Progress Report: October 1955-July 1956
Report describing technical progress on the design and construction of an Organic Moderated Reactor Experiment (OMRE), to be operated at the National Reactor Testing Station in Arco, Idaho. "This is the first report of the series and coves the period from the initiation of the project to July 31, 1956. Also included as an appendix to the report is a detailed description of the OMRE facility" (p. 3).
Date:
March 15, 1957
Creator:
Trilling, C. A.
Object Type:
Report
System:
The UNT Digital Library
Hallam Nuclear Power Facility, Reactor Operations Analysis Program: Semiannual Progress Report Number 2, March-August 1963
From summary: The full 140 element loading of the core was completed on October 10, 1962. At this point, critical operation was begun for operator training and post-critical testing purposes.
Date:
March 1, 1964
Creator:
Darley, D. K.
Object Type:
Report
System:
The UNT Digital Library
Reactor Safety Quarterly Progress Report: May-July 1956
From abstract: Impact tests on the Mark III Hanford safety element indicate that the design is mechanically adequate and does not constitute a personnel hazard.
Date:
March 15, 1957
Creator:
Miller, N. C.
Object Type:
Report
System:
The UNT Digital Library
Multi-Channel Boiling Stability for Sodium Graphite Reactors
Abstract: This report presents an analysis of coolant boiling in sodium graphite reactors.
Date:
March 1, 1962
Creator:
Cappel, H. H.
Object Type:
Report
System:
The UNT Digital Library
Reactor Shielding Design Manual
The purpose of this manual is to help an engineer or scientist to design a practical shield by making available to them the techniques and data developed by the Naval Reactors Program and Pressurized Water Reactor Program.
Date:
March 1956
Creator:
Rockwell, Theodore, III
Object Type:
Book
System:
The UNT Digital Library