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A Device for Continuous Detection of Hydrogen in Sodium

Description: 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.
Partner: UNT Libraries Government Documents Department

Steady-State Tests of a Reactor Safety Device

Description: 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.
Partner: UNT Libraries Government Documents Department

Thermodynamic Diagrams for Sodium

Description: 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.
Partner: UNT Libraries Government Documents Department

A Vapor Pressure Chart for Metals

Description: 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.
Partner: UNT Libraries Government Documents Department

A Conceptual Design of a Thorium-Uranium (233) Power Breeder Reactor

Description: 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.
Partner: UNT Libraries Government Documents Department

Neutron Leakage from the 30 Megawatt SGR-P4 Reactor

Description: 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.
Partner: UNT Libraries Government Documents Department

High Temperature Liquid Metal Circulating System

Description: 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.
Partner: UNT Libraries Government Documents Department

SRE Instrumentation and Control

Description: 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.
Partner: UNT Libraries Government Documents Department

Sodium Reactor Experiment Pump Development

Description: 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.
Partner: UNT Libraries Government Documents Department

Reference Design for an OMR-Powered 38,000-DWT Tanker

Description: 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.
Partner: UNT Libraries Government Documents Department

A Further Evaluation of the Calder Hall Type of Nuclear Power Plant

Description: 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.
Partner: UNT Libraries Government Documents Department

OMR Control-Safety Rod Component Development Tests

Description: 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.
Partner: UNT Libraries Government Documents Department

Reactivity Absorbed by Xenon-135 in the SRE

Description: 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.
Partner: UNT Libraries Government Documents Department

Organic Moderated Reactor Experiment : Safeguards Summary

Description: 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.
Partner: UNT Libraries Government Documents Department

Hot-Pressure Bonding of OMR Fuel Plates

Description: Abstract: An alluminum-clad low-enrichment, uranium-alloy fuel element of flat plate configuration has been proposed for the Organic Moderated Reactor (OMR).
Date: November 15, 1959
Creator: Alm, G. V.; Binstock, M. H. & Garrett, E. E.
Partner: UNT Libraries Government Documents Department

Plutonium: Enriched OMR Cores

Description: Abstract: The influence of plutonium on the nuclear characteristics of organic moderated cores is studied.
Date: May 1, 1960
Creator: Connolly, T. J.
Partner: UNT Libraries Government Documents Department

Maritime Organic Moderated and Cooled Reactor

Description: Introduction: This document describes the results of a six-week conceptual design study of an organic moderated and cooled reactor (OMCR) power plant adapted to a Class T-7 tanker.
Date: May 27, 1959
Partner: UNT Libraries Government Documents Department

Increasing Thermocouple Reliability for in-Pile Experiments

Description: Abstract: The results indicated that increased reliability can be obtained by using thermocouples made with insulation of increased density and/or a low thermal expansion sheath.
Date: April 20, 1965
Creator: Babbe, E. L.
Partner: UNT Libraries Government Documents Department