Technical Report Archive & Image Library (TRAIL) - 766 Matching Results

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Reactor Shielding Design Manual

Description: The purpose of this manual is to help an engineer or scientist to design a practical shield by making available to them the techniques and data developed by the Naval Reactors Program and Pressurized Water Reactor Program.
Date: March 1956
Creator: Rockwell, Theodore, III
Item Type: Refine your search to only Book
Partner: UNT Libraries Government Documents Department
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Distribution of Uranium at Low Acid : Low Uranium Concentrations into 4-1/2 Percent TBP-AMSCO

Description: Report wherein acid free uranyl nitrate hexahydrate was distributed into 4-1/2 percent TBP-Amsco 125-90W and combined with various concentrations of acid in order to study the distribution of uranium and hydrolysis effects.
Date: August 23, 1956
Creator: Andelin, Robert L.; Anderson, Edward L. & McVey, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Energy Transfer Between Modified Maxwell Distributions

Description: Abstract: "A particularly conventional modified form of Maxwell distribution is chosen. The modified expressions for (a) the energy transfer from the ions to the electrons in a plasma and (b) the brehmestrahlung from the electrons are calculated. Using the expressions some possible steady-state conditions for the ion and electron gases are derived and compared with those for the usual Maxwell distributions."
Date: September 20, 1956
Creator: Greyber, Howard D. & Bing, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Materials for Fluorine Generator Anode Assemblies

Description: Corrosion of anode assembly materials in fluorine generators is pronounced, therefore, selection of the proper materials for construction is important. Several metals and alloys have been tested for corrosion resistance when anodic in a fluorine test cell. In general, copper, copper alloys and magnesium alloys offer the best corrosion resistance.
Date: September 28, 1956
Creator: Simmons, R. E.; Rossmassler, W. R.; Hoskins, C. W. & Johnston, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Simple Leak Detector for Tritium

Description: From abstract: "An ionization chamber of the integrating type was built that could detect a tritium leak rate of 10[^-13] cc per second within a few minutes, after a gas-collecting period of 16 hours. Electronic circuitry was avoided by using a quartz fiber voltmeter to indicate the rate of discharge of the chamber."
Date: January 1957
Creator: Colvin, D. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Evaluation of the Calder Hall Type of Nuclear Power Plant

Description: Abstract: Presented herein is the preliminary design of a natural uranium, graphite moderated, CO2-cooled reactor and power plant similar to, but larger than, the British Calder Hall plant, with a net electrical output of 130 MWE.
Date: January 18, 1957
Creator: Banks, William F.; Schneider, G. A.; Morgan, William T. & Ash, E. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Physics Division Semiannual Progress Report for Period Ending September 10, 1956

Description: Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Physics Division. Descriptions of progress and studies conducted are presented. This report includes tables, and illustrations.
Date: February 12, 1957
Creator: Snell, A. H.; Fowler, J. L. & Wollan, E. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Instrumentation and Controls Division Semiannual Progress Report for Period Ending July 31, 1956

Description: Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Instrumentation and Controls Division. Descriptions of progress and studies conducted are presented. This report includes illustrations, and photographs.
Date: February 25, 1957
Creator: Borkowski, C. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Organic Moderated Reactor Experiment Progress Report: October 1955-July 1956

Description: Report describing technical progress on the design and construction of an Organic Moderated Reactor Experiment (OMRE), to be operated at the National Reactor Testing Station in Arco, Idaho. "This is the first report of the series and coves the period from the initiation of the project to July 31, 1956. Also included as an appendix to the report is a detailed description of the OMRE facility" (p. 3).
Date: March 15, 1957
Creator: Trilling, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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