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Potential Applications of Nuclear Energy in a Marine Environment

Description: 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.
Partner: UNT Libraries Government Documents Department
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Radioisotopes at Work for Agriculture

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

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
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Preliminary Test of Natural-Circulation Double-Tube Steam Generator

Description: 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.
Partner: UNT Libraries Government Documents Department
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Development of a Fuel Handling System for an Organic Moderated Reactor

Description: 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.
Partner: UNT Libraries Government Documents Department
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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
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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
open access

Terminal Status Report for the Processing Refabrication Experiment

Description: 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.
Partner: UNT Libraries Government Documents Department
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Some Thermodynamic Properties of Freon-114

Description: 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.
Partner: UNT Libraries Government Documents Department
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Hazards Analysis of the Organic Moderated Reactor Experiment

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

SRE Fuel Element Damage: An Interim Report

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Reactor Technology Report Number 11: Physics

Description: 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
Partner: UNT Libraries Government Documents Department
open access

Nuclear Superheat Quarterly Project Report: First Quarter, July-September 1959

Description: From introduction: "The purpose of the report is to set forth the development philosophy, objectives and expected results of the AEC-GE Nuclear Superheat Project."
Date: December 1, 1959
Creator: General Electric Company. Atomic Power Equipment Department.
Partner: UNT Libraries Government Documents Department
open access

Experimental Determination of the Pressure Drop Through a Pebble Bed

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

A Method of Calculating Boundary-Layer Thickness in Axisymmetric Nozzles with Laminar Hypersonic Flow

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Pressure and Thermal Stresses at a Pipe Attachment to a Sphere

Description: 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
Partner: UNT Libraries Government Documents Department
open access

Transistorized Log-Period Amplifier

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Preliminary Hazards Summary Report for the ML-1 Nuclear Power Plant

Description: 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.
Partner: UNT Libraries Government Documents Department
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In-Pile Loop Tests of GCRE Elements (I-IT and I-I'T)

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Radioactive Waste Management at Oak Ridge National Laboratory

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Specifications and Fabrication Procedures for APPR-1 Core II Stationary Fuel Elements

Description: Report regarding the design requirements and manufacturing procedures for the stationary fuel component proposed for operation in the second core loading of the Army Package Power Reactor at Fort Belvoir, Virginia.
Date: 1959
Creator: Cunningham, J. E.; Beaver, R. J.; Robertson, R. D. & Edgar, E. C.
Partner: UNT Libraries Government Documents Department
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