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Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1960 - March 1, 1961

Description: Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: April 1, 1961
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
Partner: UNT Libraries Government Documents Department
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Steam Cooled Power Reactor Evaluation - Beloyarsk (Ural) Reactor

Description: Report evaluating "the effects of nuclear steam superheating, as utilized in the Russian design, on the economics of electric power production, assuming the use of such a design in the United States" (p. 1). This report includes a description of the Beloyarsk Station and modifications made to the Russian designs for use in the United States.
Date: April 1961
Creator: Hanford Works
Partner: UNT Libraries Government Documents Department
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Fabrication Development of UO2-Stainless Steel Composite Fuel Plates for core B of the Enrico Fermi Fast Breeder Reactor

Description: Experimental work concerned with the development of an inexpensive composite fuel plate with a high burnup potential for application in a 500°C sodium environment as Core B of the Enrico Fermi Fast Breeder Reactor.
Date: April 18, 1961
Creator: Cherubini, J. H.; Beaver, R. J. & Leitten, C. F., Jr.
Partner: UNT Libraries Government Documents Department
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Runaway Analysis for a Gas Cooled Reactor

Description: From abstract: "This report presents an IBM digital computer program that solves numerically and simultaneously the equations that describe gross reactor behavior under runaway conditions."
Date: April 1961
Creator: Becker, Richard A.
Partner: UNT Libraries Government Documents Department
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Critical Path Scheduling in Maintenance

Description: Summary: The following narrative interspersed with figures and attached reference exhibits is designed to acquaint the reader with the scheduling procedure developed at ORGDP, trial results and evaluation, subsequent improvement, further application, and use in conjunction with our IBM 7090 Computer.
Date: April 10, 1961
Creator: Gritzner, C. L.; Jones, J. P. & Ellis, J. M.
Partner: UNT Libraries Government Documents Department
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High Temperature Heat Utilization in Industry

Description: Introduction: The United States Atomic energy Commission has guided the development of nuclear reactors for commercial applications for over a decade. the three most important development areas for industrial applications at the present time are for use in electric power generation, for productions of low temperature process steam, and for the supply of high temperature heat to manufacturing processes.
Date: April 1961
Creator: Ferguson, F. Alan; Towle, Leland H. & Tarrice, Richard R.
Partner: UNT Libraries Government Documents Department
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Cesium-137 Research Irradiator

Description: Abstract: A 12,000 curie cesium-137 research irradiator has been designed and installed on the Georgia Tech campus. The evaluation of the physical characteristics of the irradiator has been completed.
Date: April 20, 1961
Creator: Carter, R. W.; Palmer, R. C. & Willis, W. V.
Partner: UNT Libraries Government Documents Department
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Reconnaissance for Uranium in the Antofagasta Area, Province of Antofagasta, Chile

Description: Abstract: The Antofagasta area, in the Province of Antofagasta, Chile, was investigated in September and August 1958 by two field parties of the U.S. Atomic Energy Commission and the Instituto de Investigaciones Geológicas de Chile, who were working under a cooperative agreement between the teo governments. the purpose of the investigation was to examine the area for the possible occurrence of commercial deposits of uranium.
Date: April 1961
Creator: Knowles, Paul H.; Bowes, William A.; C., Mario Serrano & S., Rudolfo Grüenwald
Partner: UNT Libraries Government Documents Department
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Mechanical Properties of Zircaloy-2 Weld Metal

Description: Abstract: Zircaloy-2 weld metal, obtained by inert gas non-consumable-electrode welding, was subjected to tensile, strain fatigue, and creep-rupture testing.
Date: April 15, 1961
Creator: Beitscher, S.
Partner: UNT Libraries Government Documents Department
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Hazards Report for the SM-1 Core II Without Special Components

Description: Abstract: This technical report describes the changes incurred in the SM-1 by the insertion of the SM-1 Core II without special components. The SM-1 Core II components were made to specifications very nearly identical to those of SM-1 Core I. The differences consist of europium absorber sections, internal europium flux suppressors in the control rod fuel elements, and low impurity cladding. Each of the SM-1 Core II components with the exception of the five absorber sections new in SM-1 Core I were subjected to a Zero Power Experiment at the Alco Critical Facility. The results of this experiment indicate that the SM-1 Core II will have nuclear characteristics very similar to that of the SM-1 Core I. Since SM-1 Core II will be operated with the same mode of rod control, in the same core support structure, and with the same primary coolant flow conditions, the thermal characteristics should be essentially identical to that of SM-1 Core I. Also, all kinetic characteristics of SM-1 Core II should be identical to those of SM-1 Core I. This report demonstrates that there is no increase in potential for a hazardous situation at SM-1 due to the replacement of SM-1 Core I by SM-1 Core II.
Date: April 19, 1961
Creator: Gallagher, J. G.
Partner: UNT Libraries Government Documents Department
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gem-Bis(disubstitutedphosphinyl)alkanes. II. Extraction Properties of Bis(di-n-hexlphosphinyl)methane

Description: From abstract: "Bis(di-n-hexylphosphinyl)methane, HDPM, [(C6H13)2P(O)]2CH2, has been studied as an extractant for a variety of metals. HDPM was evaluated as an extractant for uranium(VI) and compared with tri-n-octylphosphine oxide, TOPO, (C8H13)3PO. In nonpolar solvents, HDPM forms a polymeric-like substance with compounds of uranium(VI). Viscosity measurements indicate that the molecular weight of this polymeric-like substance is about 100 times greater than the corresponding complex with TOPO. Polymer formation occurs only when nonpolar solvents are used as diluents for HDPM and is easily avoided by using polar solvents such as 1,2-aichlorobenzene. HDPM forms 1:1 and 2:1 complexes with uranium(VI) nitrate. Equilibrium constants for these complexes as well as that for the 2:1 TOPO complex were calculated and it was shown that the over-all constant is at least ten times larger for the HDPM complex than for the TOPO complex. The effect of concentration of various mineral acids, extractant concentration, temperature, and diluents on the extraction of uranium are discussed."
Date: April 11, 1961
Creator: Burke, Keith E.; Sakurai, Hiroshi; O'Laughlin, Jerome W. & Banks, Charles V.
Partner: UNT Libraries Government Documents Department
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Radioactivity Dissemination Near Uranium Processing Mills

Description: This report follows a preliminary survey made to study radioactive contamination of the soil (and to some extent in the air and waters) in the vicinity of seven uranium processing mills.
Date: April 1, 1961
Creator: Feldman, M. H.; Troianello, Emilio J.; Coates, G. K. & Sheehan, W. R.
Partner: UNT Libraries Government Documents Department
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