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Potential Applications of Nuclear Energy in a Marine Environment
Introduction: In January 1959, Stanford Research Institute was asked by the Office of Maritime Reactors, Division of Reactor Development, of the United States Atomic Energy Commission to identify potential applications of nuclear energy in a marine environment, excluding those involving standard commercial surface ships and direct defense applications, and to conduct a preliminary evaluation of these applications in order to determine which ones appeared most feasible for early implementation.
Date:
August 1959
Creator:
Duckstad, Eric E.
System:
The UNT Digital Library
Radioisotopes at Work for Agriculture
Introduction: The Office of Isotopes Development of the United States Atomic Energy Commission has requested that Stanford Research Institute prepare a report on the applications of radioisotopes in agriculture.
Date:
October 1959
Creator:
Homan, A. Gerlof & Tarrice, Richard R.
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
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
Power Flattening in Sodium Graphite Reactors by Spatial Variation of Moderator Properties
Abstract: In the present study, the variation of moderator composition was postulated to be effected by the inclusion of varying amounts of beryllium oxide in the graphite of an SGR.
Date:
December 15, 1959
Creator:
Connolly, T. J.
System:
The UNT Digital Library
Development of a Fuel Handling System for an Organic Moderated Reactor
Abstract: This report describes the features of several systems which were rejected as inadequate, and the evaluation of a design leading to the construction of a prototype cask and its associated equipment.
Date:
1959
Creator:
Leppard, J. A.
System:
The UNT Digital Library
Hot-Pressure Bonding of OMR Fuel Plates
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.
System:
The UNT Digital Library
Maritime Organic Moderated and Cooled Reactor
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
Creator:
unknown
System:
The UNT Digital Library
Terminal Status Report for the Processing Refabrication Experiment
Introduction: A low-capacity, low-decontamination plant can be built, as part of a power reactor complex, to avoid long distance transfer of fuel to a high-capacity aqueous processing plant. Activation of such a complex, with the processing plant adjacent to the reactor it serves, could decrease the cost of the integrated fuel cycle. The study of this concept is a major objective of the Processing Refabrication Experiment (PRE).
Date:
November 15, 1959
Creator:
Sinizer, D. I.; Mattern, K. L. & Kendall, E. G.
System:
The UNT Digital Library
Some Thermodynamic Properties of Freon-114
Introduction: The thermodynamic properties of Freon-114 presented herein supplement those of Volume I and encompass a range of temperature above the critical to 400 F &176 F.
Date:
September 3, 1959
Creator:
Van Wie, N. H. & Ebel, Robert A.
System:
The UNT Digital Library
Hazards Analysis of the Organic Moderated Reactor Experiment
Introduction: The description of the Organic Moderated Reactor Experiment, (OMRE), its location, its safety system, and operative procedures have been previously detailed. The present report, although dealing with the subject of OMRE safety, has the more detailed intent of (1) determining the behavior of the OMRE under extremely unlikely sets of conditions; and (2) providing additional design information in the areas of reactivity coefficients, burnout heat flux, and reactor control.
Date:
December 15, 1959
Creator:
Williams, R. O., Jr.; Allen, W. O.; Ash, E. B.; Scott, W. W.; Shimazaki, T. T.; Sletten, H. L. et al.
System:
The UNT Digital Library
SRE Fuel Element Damage: An Interim Report
Abstract: During the course of power run 14 on the Sodium Reactor Experiment (SRE) at low power, the temperature difference among various fuel channels was found to be undesirably high. Normal operating practices did not succeed in reducing this temperature difference to acceptable values and on July 26, 1959, the run was terminated.
Date:
November 30, 1959
Creator:
Jarrett, A. A.
System:
The UNT Digital Library
Reactor Technology Report Number 11: Physics
Quarterly report issued by the Knolls Atomic Power Laboratory to report to the industry on developments in unclassified reactor technology. This issue focuses on physics information.
Date:
December 1959
Creator:
unknown
System:
The UNT Digital Library
Ionium Recovery Plant Design Report: Topical Report
This report documents the study of the recovery of thorium by solvent extraction in pilot plant pulse columns, using a filtered liquor from nitric acid digestions of the raffinate cake produced by the ethyl ether extraction of uranium from pitchblende.
Date:
April 15, 1959
Creator:
Edwards, R. M.; Fariss, R. H. & Werkema, R. G.
System:
The UNT Digital Library
Interim Report on Investigation of Dynamic Characteristics of Relays: June-July 1959
From scope of work: This report investigates the dynamic characteristics of sealed military type relays as affected by applied coil voltage and/or current, temperature, spring tension, contact force, contact overtravel, and mechanical clearances.
Date:
September 1959
Creator:
unknown
System:
The UNT Digital Library
Experimental Determination of the Pressure Drop Through a Pebble Bed
Abstract: "The pressure drop associated with the flow of air through a cylindrical bed of spherical pebbles has been investigated experimentally. The results of this investigation are reported here."
Date:
September 1959
Creator:
Randall, D. E. & Millwright, S. S.
System:
The UNT Digital Library
A Method of Calculating Boundary-Layer Thickness in Axisymmetric Nozzles with Laminar Hypersonic Flow
Abstract: "The excellent agreement between measured boundary layer thickness and thickness calculated by Sivells and Payne recommends their method for calculating turbulent boundary layer growth in axisymmetric hypersonic nozzles. It was thought worthwhile to adapt their approach to the laminar boundary layer. This analysis, along with a limited amount of corroborating data, is presented herein."
Date:
October 1959
Creator:
Johnson, Arlo F.
System:
The UNT Digital Library
Pressure and Thermal Stresses at a Pipe Attachment to a Sphere
Abstract: Design nomographs and equations have been prepared for determining the bending stresses and hoop stresses at the junction of a cylinder and sphere when: (1) Internal pressure exists in the sphere and (2) There is a difference in average temperature between the cylinder and the sphere. A correlation of calculated stresses and photoelastically determined stresses for models with internal pressure is presented.
Date:
September 21, 1959
Creator:
Deagle, Lorenzo
System:
The UNT Digital Library
Transistorized Log-Period Amplifier
Abstract: A log-period amplifier which is combined with power supply on a rack-mounted chassis with a 7-in. panel is described.
Date:
June 1959
Creator:
Wade, E. J. & Davidson, D. S.
System:
The UNT Digital Library
Strontium Program: Quarterly Summary Report, May 29, 1959
From Abstract: "This report is one of a sequence of quarterly reports, each designed to up-date its predecessor beginning with HASL-42, "Environmental Contamination from Weapon Tests". Herein are presented data which have accrued since HASL-55. Levels of strontinum-90 in fallout, milk, air, water, vegetation, foods, and bone are given, based on data available from February 1, 1959 to May 20, 1959."
Date:
May 29, 1959
Creator:
Hardy, Edward P., Jr. & Klein, Stanley
System:
The UNT Digital Library
Oak Ridge National Laboratory Instrumentation and Controls Division Annual Progress Report: 1958
Report documenting ongoing research and development carried out by the Instrumentation and Controls Division of the Oak Ridge National Laboratory.
Date:
June 24, 1959
Creator:
Oak Ridge National Laboratory. Instrumentation and Controls Division.
System:
The UNT Digital Library
Preliminary Hazards Summary Report for the ML-1 Nuclear Power Plant
From abstract: "Neutronic characteristics, the control and instrumentation system, equipment description and plant safety considerations of the ML-1 (mobile, low power) nuclear power plant. The site is described with reference to geology, climate, and population density."
Date:
September 30, 1959
Creator:
Linenberger, G. A.
System:
The UNT Digital Library
In-Pile Loop Tests of GCRE Elements (I-IT and I-I'T)
Report documenting two in-pile loop experiments conducted at the Battelle Research Reactor-Gas Cooled Reactor (BRR-GCR). These experiments test heat transfer calculations and the behavior of the fuel element under severe thermal-cycling conditions.
Date:
July 2, 1959
Creator:
Nakazato, S.; Williams, P. M. & Wilson, W. D.
System:
The UNT Digital Library
Radioactive Waste Management at Oak Ridge National Laboratory
Report documenting "[t]he collection, treatment, disposal, and monitoring of radioactive wastes (solid, liquid, and gaseous) at Oak Ridge National Laboratory" (p. 2).
Date:
1959
Creator:
Browder, F. N.
System:
The UNT Digital Library