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A Versatile Bubble-Chamber Track Measuring Stage

Description: Technical report describing a bubble chamber film track measuring stage designed for maximum versatility that was build at Brookhaven National Laboratory. The report includes photographs and diagrams of the device.
Date: March 1962
Creator: Ayer, Frederick, II & Bolze, Ernest M.
Partner: UNT Libraries Government Documents Department
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A Bubble Chamber Track-Centering Device with Digitized Output

Description: Technical report describing "A means for automatically determining the coordinates of a point at the center of a bubble chamber track." from the abstract.
Date: March 1962
Creator: Ayer, Frederick.; Pickup, Eric.; Rappe, Edwin F. & Wall, Gaylord.
Partner: UNT Libraries Government Documents Department
open access

͟v͟ic-Dioximes as Analytical Reagents

Description: This technical report discusses the synthesis of vic-dioximes, the analysis of vic-dioximes, the structure of vic-dioximes, the structure of metal(II)-vic-dioxime complexes, and analytical applications of this research. The report includes tables and figures that accompany the report's contents and findings.
Date: March 19, 1962
Creator: Banks, Charles V.
Partner: UNT Libraries Government Documents Department
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Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 2. Plant Conceptual Studies

Description: Second part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. II-i).
Date: March 1962
Creator: Combustion Engineering, inc. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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Thermal Analysis of Type 3 Elements in the SM-1, SM-1A and PM-2A Cores

Description: Report describing a study which analyzed thermal characteristics of Type 3 elements planned for installation in the SM-1, SM-1A and PM-2A plants, for both steady state and loss of flow transient conditions. Results of this analysis for steady state conditions indicate that the SM-1, SM-1A and PM-2A Type 3 cores will operate safely at design and scram conditions.
Date: March 30, 1962
Creator: Davidson, S. L. & Segalman, I.
Partner: UNT Libraries Government Documents Department
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On the Structure of Sperm Whale Myoglobin. [Part] 1, The Amino Acid Composition and Terminal Groups of the Chromatographically Purified Protein

Description: The report objective is to establish the amino acid composition of sperm whale myoglobin. From Summary: "The homoprotein that comprises 96% by weight of the protein present in crystalline sperm whale myoglobin may be received into at least five components by chromatography on the carboxylic resin IRC-50."
Date: March 26, 1962
Creator: Edmundson, A. B. & Hirs, C. H. W.
Partner: UNT Libraries Government Documents Department
open access

Separation of Iron by Liquid-Liquid Column Extraction

Description: From abstract: "Iron(III) can be separated from many elements by extraction from 6 to ͟8M hydrochloric acid. The extraction is carried out by passing the aqueous hydrochloric acid solution through a column packed with 2-octanone adsorbed onto a poly-fluorocarbon resin. Fluoride, phosphate, sulfate or citrate cause no interference. Traces if iron(III) can be separated quantitatively from large amounts of copper(II) or zinc(II); traces of titanium(IV) can be separated from large amounts of iron(II… more
Date: March 21, 1962
Creator: Fritz, James S. (James Sherwood), 1924- & Hedrick, C. E.
Partner: UNT Libraries Government Documents Department
open access

On Certain Finite Difference Schemes for the Equations of Hydrodynammics

Description: "We will consider two finite difference schemes for the solution of the Navier-Stokes equations in one space dimension. The first is a method used by Lax and Wendroff. The second method is based on an approximate solution of the centered, implicit difference equations. Since this approximate solution is obtained by successive substitutions, we will refer to this second method as an iterative method."
Date: March 1, 1962
Creator: Gary, John William
Partner: UNT Libraries Government Documents Department
open access

Annual Progress Report on Fuel Element Development for Fiscal Year 1961

Description: Report that reviews the yearly progress made in Reactor Fuel and Materials Development Program at the Engineering Test Reactor (ETR) and Materials testing reactor (MTR).
Date: March 9, 1962
Creator: Gibson, G. W. & Shupe, O. K.
Partner: UNT Libraries Government Documents Department
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Fort McClellan Radiological Instruction Area (ARMS-II)

Description: Report documenting the survey of the U. S. Army Chemical Corps Schoo, Radiological Instruction Area, Fort Mclellan, Alabama. This survey measures radiation an d gamma-ray flux in an approximately one square mile area.
Date: March 26, 1962
Creator: Guillou, R. B.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Zirconium Hydride as Moderator in Integral, Boiling Water-Superheat Reactors

Description: This report summarizes the results and conclusions of a study made to evaluate the merits of using zirconium hydride as a solid moderator in an integral boiling water-nuclear superheat reactor of the pressure vessel type.
Date: March 1, 1962
Creator: Gylfe, J. D.; Rood, H.; Greenleaf, J.; Balkwill, K.; Prem, L. & Goldfisher, L.
Partner: UNT Libraries Government Documents Department
open access

PL-3 Phase I Task 3 Research and Development Report

Description: Abstract: This technical report summarizes the results of research and development tasks performed during Phase I of this contract and presents recommendations for future development work. Work is reported in the areas of plant assembly and relocation, housings and footings, waste heat dissipation, instrumentation, refueling systems, waste disposal, shielding, core nuclear thermal and hydraulic studies, gaseous waste processing (BWR), and critical experiments on a 5 x 5 array of Type 3 fuel ele… more
Date: March 12, 1962
Creator: Humphries, G. E.
Partner: UNT Libraries Government Documents Department
open access

Preliminary Technical Report SM-1 Core III with Type 3 Elements

Description: Abstract: This preliminary technical report covers design of the SM Type 3 element, its use .in.. SM-1 Core III, and planned use in the Type 3 Core for PM-2A. The Type:3 element characteristics are compared with Type 1 (SM-1 Core I) element nuclear, metallurgical, thermal and hydraulic characteristics and fabrication. The effect of using the Type 3 element in SM-1 Core III and. its planned use in a Type 3 Core for PM-2A is discussed with regard to operation, shielding, reactor safety and all co… more
Date: March 30, 1962
Creator: Inglima, J. N.; Beam, R. H.; Davidson, S. L. & Edgar, E. C.
Partner: UNT Libraries Government Documents Department
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Summary Report of Analysis of Physics Measurements Performed on SM-1 Core I

Description: Abstract: This technical report contains a comprehensive analysis of the nuclear characteristics of the SM-1 Core I. Comparison of analytical and experimental results for neutron ages and core reactivities of a variety of cases investigated shows that the MUFT III with P-1 slowing down approximation gives the best results. At startup the core reactivity and rod bank worth under various operating conditions are investigated and compared to experiment. Core lifetime was calculated to be 16.8 MWYR… more
Date: March 30, 1962
Creator: Lois, L.; Paluszkiewicz, S.; Fried, B. E. & Beam, R. H.
Partner: UNT Libraries Government Documents Department
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Startup Testing of the PM-2A Nuclear Power Plant

Description: Abstract: A detailed description of the PM-2A reactor, primary system and instrumentation is presented. A general description of the secondary system and plant arrangement at Camp Century, Greenland is included. The results of the startup physics, shielding, thermal and hydraulics and radiochemistry test are presented. the analysis performed on the shielding and thermal and hydraulic tests is included. The shielding problem at startup and the shielding modification made to the plant are describ… more
Date: March 31, 1962
Creator: McCool, W. J.; Ryan, R. M.; Richards, W. M. S.; Bradley, P. L.; Stephenson, L. D. & Cox, J. F.
Partner: UNT Libraries Government Documents Department
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Thorium-Molybdenum Phase Diagram

Description: From abstract: "The phase diagram of the thorium-molybdenum alloy system has been determined to be the eutectic type with a eutectoid reaction associated with the thorium alpha-beta transformation. X-ray, thermal, electrical resistance and metallographic methods have established the eutectic point at 1380 ± 10°C and 7.0 ± 0.5 wt % molybdenum. A eutectoid reaction is proposed at 1358 ± 5°C and less than 0.1 wt % molybdenum. No solubility of thorium in molybdenum was detected at 1325°C."
Date: March 27, 1962
Creator: McMasters, O. D.; Palmer, P. E. & Larsen, W. L.
Partner: UNT Libraries Government Documents Department
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Magnetic Force Welding Sintered Aluminum Powder Materials

Description: Report discussing the use of sintered aluminum powder for nuclear fuel cladding. This report includes descriptions of pertinent materials and experimental procedures.
Date: March 1962
Creator: Mills, L. E.
Partner: UNT Libraries Government Documents Department
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Shielding Measurements at the SM-1 Reactor : June 1961

Description: Abstract: Neutron flux and gamma radiation measurements through the SM-1 primary shield were made at the startup of Core II in June 1961. They extend previous measurements (APAE-35) both vertically and horizontally in the primary shield and in the rod drive pit. Dose rate measurements on spent fuel elements under water are also reported.
Date: March 16, 1962
Creator: Moote, F. G. & Obrist, C. H.
Partner: UNT Libraries Government Documents Department
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