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Steady-State Tests of a Reactor Safety Device
Introduction: This is the fourth report in a series of reports dealing in particular with a reactor safety device of a double diaphragm type.
Date:
December 15, 1960
Creator:
Springer, T. H.
System:
The UNT Digital Library
A Device for Continuous Detection of Hydrogen in Sodium
Abstract: A device to detect the presence of hydrogen in sodium has been developed. Such a device, installed in a sodium heated steam generator, would signal the presence of water in the sodium resulting from a leak in the sodium-water barrier.
Date:
December 15, 1960
Creator:
Strahl, H.
System:
The UNT Digital Library
Analog Models for HNPF Control and Protection Studies
Abstract: This report, intended as a working document, contains analytic representations and analog models of the Hallam Nuclear Power Facility as used in studies of the Control and Protection Systems.
Date:
June 15, 1964
Creator:
Dunsmore, C. L.
System:
The UNT Digital Library
Thermodynamic Diagrams for Sodium
From abstract: This paper presents temperature-entropy and Mollier charts for sodium, and describes briefly the method used for their construction, based upon data from the literature.
Date:
July 13, 1950
Creator:
Inatomi, T. H. & Parrish, W. C.
System:
The UNT Digital Library
A Vapor Pressure Chart for Metals
From conclusions: There is a close enough correlation for most metals to give the chart some utility in estimating vapor pressure of metals.
Date:
July 10, 1952
Creator:
Loftness, Robert L.
System:
The UNT Digital Library
A Conceptual Design of a Thorium-Uranium (233) Power Breeder Reactor
From abstract: A conceptual design study has been performed for a sodium cooled, graphite moderated, thermal power-breeder reactor utilizing the Thorium-Uranium 233 breeding cycle. Several aspects of the design of the system are considered but no attempt has been made to supply all the details. It appears that the design presented is feasible and will allow the production of economic power as well as full utilization of thorium resources.
Date:
February 1, 1954
Creator:
Henrie, J. O. & Weisner, E. F.
System:
The UNT Digital Library
Neutron Leakage from the 30 Megawatt SGR-P4 Reactor
Abstract: The fast and thermal neutron leakage from the 30 megawatt SGR-P4 reactor has been studied by three independent methods.
Date:
August 21, 1953
Creator:
Fillmore, F. L.
System:
The UNT Digital Library
Operations Handbook for the North American Aviation, Inc. Research Reactor, Model L-3
Report describing reactor components, operational characteristics, and operating instructions for the Model L-3 research reactor.
Date:
December 11, 1953
Creator:
North American Aviation
System:
The UNT Digital Library
High Temperature Liquid Metal Circulating System
Introduction: The purpose of this experiment was to demonstrate that a liquid metal heat transfer system could be built and operated at very high temperatures.
Date:
August 1, 1954
Creator:
Keen, R. D.
System:
The UNT Digital Library
SRE Instrumentation and Control
Introduction: This memo gives a general description of the components and equipment affecting the control of the SRE, and the equipment associated with all reactor services.
Date:
May 21, 1956
Creator:
Hall, R. J.
System:
The UNT Digital Library
Sodium Reactor Experiment Pump Development
Design and operational techniques are described for a freeze seal type centifugal pump for use in the Sodium Reactor Experiment.
Date:
January 1, 1957
Creator:
Cygan, R.
System:
The UNT Digital Library
An Evaluation of the Calder Hall Type of Nuclear Power Plant
Abstract: Presented herein is the preliminary design of a natural uranium, graphite moderated, CO2-cooled reactor and power plant similar to, but larger than, the British Calder Hall plant, with a net electrical output of 130 MWE.
Date:
January 18, 1957
Creator:
Banks, William F.; Schneider, G. A.; Morgan, William T. & Ash, E. B.
System:
The UNT Digital Library
Reference Design for an OMR-Powered 38,000-DWT Tanker
Abstract: This report presents a reference design of an organic moderated and cooled reactor for the propulsion of a 38,000-dwt tanker.
Date:
March 18, 1957
Creator:
Gimera, R. J. & Stanbridge, R. E.
System:
The UNT Digital Library
A Further Evaluation of the Calder Hall Type of Nuclear Power Plant
Abstract: This report presents the results of plant optimization studies and cost estimates of the reference design for a natural uranium, graphite moderated, gas-cooled reactor and power plant which was described in NAA-SR-1833.
Date:
June 28, 1957
Creator:
Banks, William F.
System:
The UNT Digital Library
Graphical Aids in the Calculation of the Shielding Requirements for Spent U²³⁵ Fuel
Abstract: The data presented herein, in the form of graphs, can be used to obtain the value of this energy.
Date:
November 15, 1957
Creator:
Ashley, R. L.
System:
The UNT Digital Library
Application of Fast Neutron Removal Theory to the Calculation of Thermal Neutron Flux Distributions in Reactor Shields
Abstract: A calculational method is presented which may be used to determine fast and thermal neutron flux distributions at deep neutron penetrations in hydrogenous shields.
Date:
1958
Creator:
Duncan, David S. & Whittum, H. O., Jr.
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.
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.
System:
The UNT Digital Library
OMR Control-Safety Rod Component Development Tests
Abstract: A magnetic-jack control-safety rod is under development for the 45.5 thermal megawatt Organic Moderated Reactor. The rod is "unitized," i.e., the poison element, drive, position indicator, and shock absorber are contained in a compact assembly which is inserted in a regular fuel channel opening in the core. Tests to develop components capable of operating under these conditions are described and results are reported.
Date:
September 15, 1959
Creator:
Howell, J. D.
System:
The UNT Digital Library
Reactivity Absorbed by Xenon-135 in the SRE
Abstract: The measurement and calculation of the reactivity absorbed by Xe135 as functions of time after shutdown for the SRE are described.
Date:
January 28, 1960
Creator:
Woodruff, R. W.
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.
System:
The UNT Digital Library
The Closest Packing of Spheres (A Unifying Basis for Crystal Structures)
Abstract: An intuitive approach to the understanding of crystal structures is presented in terms of the concept of the closest packing of spheres.
Date:
July 30, 1961
Creator:
Gehman, William G.
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.
System:
The UNT Digital Library
Coolant Flow and Outlet Temperature: Computer-Monitors for the Hallam Nuclear Power Facility Plant Protective System
Abstract: The design and application of two computers for the HNPF protective system is discussed.
Date:
September 15, 1961
Creator:
Schlein, H.
System:
The UNT Digital Library