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Studies Regarding the Role of Wyoming Natural Gas in Precipitating Primary uranium Minerals from Pregnant Solutions

Description: Abstract: This project was designed to test the chemical feasibility of depositing of depositing a primary uranium mineral from a pregnant solution by exposing the solution to natural gas in an environment favorable to such deposition.
Date: May 11, 1956
Creator: Sims, Harry M. & Smith, Fred L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SRE Instrumentation and Control

Description: Introduction: This memo gives a general description of the components and equipment affecting the control of the SRE, and the equipment associated with all reactor services.
Date: May 21, 1956
Creator: Hall, R. J.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation of Thorium Slugs

Description: From abstract: "Ninety-two thorium slugs were irradiated in the Hanford piles to study the dimensional stability of the metal. The burnups that were incurred covered the range from 300 to 2800 ppm of the Th232. Slugs with burnups as high as 800 ppm were examined for visual and dimensional changes. The dimensional stability of these slugs was excellent, and no significant corrosion occurred on the aluminum cans. A cursory examination of slugs with burnups of greater than 800 ppm showed no gross … more
Date: May 1956
Creator: Marshall, Robert P.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor Analysis for the Army Package Power Reactor No. 1

Description: Abstract: The reactor analysis of the critical experiment and the APPR-1 resulted in a loading of the APPR-1 of 31.096 gm of B-10 with 22.5 kg U-335. This loading will result in adequate reactivity for a core life of 13 MWYR based on uniform burnup of U-335 and B-10. Calculations indicate that five of the seven control rods provided are more than adequate to shut the reactor down at any time. The temperature coefficient of reactivity should be at least -2 x 10-4 [delta] K/0F.
Date: May 29, 1956
Creator: Gallagher, J. G.; Giesler, H. W.; Johnson, W. R.; Fairbanks, F. B.; Oby, P. V. & Crouch, A. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor Analysis for the Army Package Power Reactor No. 1

Description: Abstract: The reactor analysis of the critical experiment and the APPR-1 resulted in a loading of the APPR-1 of 31.096 gm of B-10 with 22.5 kg U-335. This loading will result in adequate reactivity for a core life of 13 MWYR based on uniform burnup of U-335 and B-10. Calculations indicate that five of the seven control rods provided are more than adequate to shut the reactor down at any time. The temperature coefficient of reactivity should be at least -2 x 10-4 [delta] K/0F.
Date: May 29, 1956
Creator: Gallagher, J. G.; Giesler, H. W.; Johnson, W. R.; Fairbanks, F. B.; Oby, P. V. & Crouch, A. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Summary Hazards Report on Enriched Fuel Element Loading for the BNL Research Reactor

Description: Report issued by the Brookhaven National Laboratory discussing a hazards report on replacing the research center's current fuel elements with new highly enriched elements. As stated in the introduction, "this report is a summary of the studies, both theoretical and experimental, which have been made so far of the nuclear properties of the "new" pile, of the stability of the new fuel elements, and of the safety and practicability of operation of the "new" pile" (p. 2). This report includes table… more
Date: May 24, 1956
Creator: Corngold, N.; Kaplan, I.; Chernick, J.; Gurinsky, D. H. & Fowell, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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