77 Matching Results

Search Results

Results: 1 - 24 next
open access

Salt Bath Heat Transfer Rates for Uranium Plate

Description: Experiment to study temperature conditions during a five-minute heating cycle in the annealing of uranium sheets used as fissile material.
Date: February 1, 1962
Creator: Burditt, R. B.
Partner: UNT Libraries Government Documents Department
open access

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 1. Cost Analysis and Future Development

Description: First 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. I-ii).
Date: April 1962
Creator: Combustion Engineering, inc. Nuclear Division.
Partner: UNT Libraries Government Documents Department
open access

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
open access

Ionic Equilibria and Anion Exchange of Uranyl Sulfate Solutions

Description: Theoretical investigation on the nature of ion exchange of acidified uranyl sulfate solutions with Dowex 21K, a strong base ion exchange resin.
Date: September 28, 1962
Creator: Stein, P. E.
Partner: UNT Libraries Government Documents Department
open access

A Technical and Economic Evaluation of Solid-Fuel Gasification using Nuclear Heat: Production of Pipeline Gas, Liquid Fuels, and Chemicals from Lignite and Bituminous Coal

Description: From abstract: Results are reported of a study to determine the most economical method of utilizing nuclear heat to gasify a North Dakota lignite and a West Virginia bituminous coal so that the resulting gas is suitable as a source of synthesis gas for fuels and chemicals.
Date: November 30, 1962
Partner: UNT Libraries Government Documents Department
open access

Supplement to Reactor Containment Design Study

Description: Summary: Report SL-1868 is a technical and economic feasibility study of four containment methods, i.e., standard containment, pressure relief, pressure supression and low pressure containment, for 44 MWe direct cycle and 180 and 300 MWe dual cycle boiling water reactor plants.
Date: April 23, 1962
Creator: Johnson, R. A. & Nelson, I.
Partner: UNT Libraries Government Documents Department
open access

Reactor Technology Report Number 22: Chemistry

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 chemistry information.
Date: September 1962
Partner: UNT Libraries Government Documents Department
open access

Thermal Stress Testing of Beryllium Oxide Moderator Shapes

Description: Abstract: Perforated BeO plates were thermal shock tested to evaluate the effect of: (1) localized temperature variations adjacent to the perforations, and (2) radial gradients across the entire plate.
Date: August 1, 1962
Creator: Sujata, H. L.; King, M. & Waters, F. J.
Partner: UNT Libraries Government Documents Department
open access

Corrosion of Zircaloy in Crevices under Nucleate Boiling Conditions

Description: Abstract: The MSAR corrosion test loop was used to study the effect of VKE-shaped crevices on the corrosion resistance of Zircaloy under boiling heat-transfer condtions in both ammoniated and lithiated water at pH 10.5.
Date: April 1962
Creator: Anderson, W. Kermit & McGoff, M. J.
Partner: UNT Libraries Government Documents Department
open access

Capsule Irradiation of Unalloyed Uranium at High Temperatures

Description: Abstract: Cast and Wrought specimens and restrained wrought specimens of unalloyed uranium were irradiated in the Materials Testing Reactor, as the first in a series of experiments to develop fuel materials for sodium cooled reactors.
Date: August 15, 1962
Creator: Harrington, D. G. & Newton, J. 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

Fast Neutron Flux Measurements and Analysis in SM-1 and PM-2A Core and Vessel Mockups

Description: Abstract: This technical report contains a summary of experimental and analytical work performed on cold clean SM-1 Core II with special components and PM-2A Core I each with thermal shield and vessel mockups. The purpose of this work was to define the neutron intensity and spectra to which the pressure vessels are subjected in order to assess the effect of irradiation on the vessel lifetimes. The radial distributions of the energy dependent neutron flux per unit power in the core and vessel m… more
Date: March 31, 1962
Creator: Sontheimer, K. C.; Kemp, S. N.; Lois, L.; Clancy, E. F. & McCool, W. J.
Partner: UNT Libraries Government Documents Department
open access

Investigation of 17-4 PH Steel Components Used in SM-1, SM-1A, PM-2A Reactor Plants

Description: Abstract: This technical report covers the investigation of 17-4 PH steel components used in the SM-1, SM-1A and PM-2A nuclear power plants, which consist of control rod drive racks, pinions, seal shafts and associated parts. Evidence supporting the continued use of 17-4 PH steel in these applications is presented. Alco's current procurement and processing specifications for 17-4 PH steel are included. The evidence presented is in the form of stress calculations, test and environmental data and… more
Date: January 23, 1962
Creator: Haraway, E. S. & Saccocio, R. M.
Partner: UNT Libraries Government Documents Department
open access

PM-2A Core II Zero Power Experiment

Description: Abstract: This technical report covers the zero power experiments performed on PM-2A Core II at the Alco Critical Facility. PM-2A Core II is the first replacement core for a portable pressurized reactor at Camp Century, Greenland. Core II is the same as Core I with the exception that Core II has an increased burnable poison (B-10) content. The zero power experiment consisted of fuel element uniformity test; core assembly test, development of an on-site loading procedure and an analysis of exper… more
Date: March 30, 1962
Creator: Walthousen, L. D.; Mageean, J. V.; Raby, T. M. & Lee, D. H.
Partner: UNT Libraries Government Documents Department
open access

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

Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1962 - September 1, 1962

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: October 1, 1962
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Collins, William R., Jr.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen