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Carbide Fuel Development: Phase 1 Report, Period of May 15 to September 15, 1959

Description: From foreword: This report describes the work accomplished including the Conceptual Design task and the initial results of the tasks on Facility Design and Fabrication, Fuel Fabrication and Evaluation, and Fuel Reprocessing.
Date: October 15, 1959
Creator: Bolomey, R.; Lazerus, S.; Sapir, J.; Sofer, G.; Steinmetz, H.; Strasser, A. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Ionium Recovery Plant Design Report: Topical Report

Description: 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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Strontium Program: Quarterly Summary Report, May 29, 1959

Description: 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
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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