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Operating Manual for the CP-5 Reactor

Description: There are two General Operating Conditions for the CP-5 Reactor. These involve 1. start-up of the reactor following extended shutdowns which might be associated with a complete fuel removal and reloading, and 2. essentially continuous operation of the reactor with only brief shutdowns.
Date: January 1, 1956
Creator: {{{name}}}
Partner: UNT Libraries Government Documents Department
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Progress Relating to Civilian Applications During December, 1955

Description: A report about the properties of dilute uranium alloys. The mechanical properties of cold worked sirconium and zircaloy 2 at temperatures up to 500 C ore being determined.
Date: January 1, 1956
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Partner: UNT Libraries Government Documents Department
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Progress Relating to Civilian Applications During January, 1956

Description: A report which discusses the response of dilute uranium alloys to heat treatment with the ultimate objective of developing high-strength fuel elements.
Date: February 1, 1956
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Partner: UNT Libraries Government Documents Department
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Progress Relating to Civilian Applications During February, 1956

Description: A report about aluminum-clad fuel elements, fuel-element development, zirconium uranium alloys, corrosion of zirconium, and reactor material development.
Date: March 1, 1956
Creator: Dayton, Russell W.
Partner: UNT Libraries Government Documents Department
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Progress Relating to Civilian Applications During April, 1956

Description: A report about elevated-temperature properties of dilute uranium-aluminum and uranium-zirconium alloys. Hot-hardness measurements show that small amounts of wither aluminum or zirconium increase the hardness of uranium at elevated temperatures.
Date: May 1, 1956
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Partner: UNT Libraries Government Documents Department
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Shielding Requirements for the Army Package Power Reactor

Description: Abstract. The design, selection, and calculation of the Army Package Power Reactor shielding are described. The APPR-1, a prototype of a package reactor for remote locations, has a primary shield of iron and water. this shield has been adopted to permit fast erection and to provide low transported weight. economically, including transportation cost, the iron water shield is better than a lead water shield and is competitive with a concrete shield for a remote site. Because of the location at… more
Date: May 1, 1956
Creator: Meem, J. L. (James Lawrence). & Fairbanks, F. B.
Partner: UNT Libraries Government Documents Department
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Progress Relating to Civilian Applications During May, 1956

Description: A report about mechanical properties of dilute uranium alloys are being investigated in an effort to develop a high-strength alloy for fuel elements. Elevated temperature tensile tests were made on two dilute uranium-aluminum alloys, and several ternary alloys were arc melted.
Date: June 1, 1956
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Partner: UNT Libraries Government Documents Department
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Progress Relating to Civilian Applications During July, 1956

Description: A report based on a study about the factors which affect the amount of chemical reaction between water and Zircaloy 2 at high temperatures. Also, experimental programs for the measurement of radiation emissivity, chemical reaction rates, and diffusion rates have been completed.
Date: August 1, 1956
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Partner: UNT Libraries Government Documents Department
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A Binary-to-Decimal Converter

Description: A system of standard electronic logical circuits which stores a seven-bit binary member, converts the binary number to its decimal equivalent, and then indicates the decimal equivalent in direct-reading neon lights is described.
Date: September 1, 1956
Creator: Stearns, Samuel D.
Partner: UNT Libraries Government Documents Department
open access

Results of Experiment 1: FCE Calibration With BORAX Core

Description: Summary: The justification of using polyethylene whose hydrogen density of 0.132 gm/cm³ with a distributed void of 15.9 percent as a mockup of water at 70°F and having a hydrogen density of 0.111 gm/cm³ was tested in the FCE. A mockup close to the BORAX core was built and its critical mass determined. Corrections were calculated for differences in the hydrogen desnity and self shielding of the fuel. The effective FCE critical mass agreed with that of the BORAX core to within one percent.
Date: October 1, 1956
Creator: Starr, E. & Toops, Edward Chassell
Partner: UNT Libraries Government Documents Department
open access

Enrico Fermi Fast Breeder Reactor Plant

Description: This report contains a description of the reactor plant portion of the Enrico Fermi Atomic Power Plant, with emphasis on the reactor system. Since this plant contains a developmental reactor, emphasis has been placed on reactor safety and on achieving reliable operation. The design is conservative and is flexible enough to permit incorporation of the results of developmental programs, which include nonnuclear, full-scale component test facility operations, and nuclear experiments, such as criti… more
Date: November 1, 1956
Creator: U.S. Atomic Energy Commission
Partner: UNT Libraries Government Documents Department
open access

MTR Technical Branch Quarterly Report, Third Quarter

Description: Quarterly report for the technical branch of the Materials Testing Reactor of Idaho. Includes current developments and experiments.
Date: November 1, 1956
Creator: Conner, W. P.
Partner: UNT Libraries Government Documents Department
open access

Progress Relating to Civilian Applications During October, 1956

Description: A report about the use of clad specimens to successfully measure the thermal conductivity of irradiated uranium.
Date: November 1, 1956
Creator: Dayton, Russell W. & Tipton, Clyde R., Jr.
Partner: UNT Libraries Government Documents Department
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