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Operation of the ORNL Graphite Reactor and the Low-Intensity Test Reactor — 1955 LITR Flux Traverses

Description: The ORNL Graphite Reactor operated very well during 1955. The downtime was low, only 8.6%. The fuel in the bonded slugs did not perform as well in 1955 as in 1954. Much of the trouble was undoubtedly due to growth of slugs which were not beta-transformed. It is known that some slugs had grown over 1/2 in. The automatic central system installed in 1954 continued to operate satisfactorily. The cooling system gave minor trouble when one of the 900-hp fan meters had to be replaced because of shorts… more
Date: September 10, 1956
Creator: Rupp, A. F. & Cox, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Project Quarterly Progress Report for Period Ending July 31, 1955

Description: Construction of the HRT reactor shield tank was completed, and the inside surfaces were painted. The roof structure for the tank is being assembled in preparation for an acceptance pressure test. Service piping and instrument lines are being installed in the central room area by ORNL craft forces. This work is approximately 50% complete. Fabrication of all temperature system components, except the blanket outer storage tanks, has been completed.
Date: October 10, 1955
Creator: McDuffie, H. F. & Kelly, D. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Fused Salt—Fluoride Volatility Process for Recovery and Decontamination of Uranium

Description: A preliminary chemical flowsheet is presented of a fluoride volatility process for recovering and decontaminating uranium from heterogeneous reactor fuels after dissolution in a fused salt. In laboratory work, a gross β decontamination factor of > 10 4 was obtained in the fluorination of a UF4-NaF-ZrF4 melt by passing the product UF6 through NaF at 650°C. The solubility of UF6 in molten NaF-ZrF4 was shown in kinetic studies to cause a lag in the evolution of UF6 from the fluorinator. Corrosion … more
Date: October 10, 1955
Creator: Cathers, G. I. & Bennett, M. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Solvent Extraction Method for Neptunium (237) Analysis

Description: Technical report describing a rapid and quantitative radiochemical method for the analysis of neptunium (237). This method is based on the extraction of neptunium (IV) with thenoyl-trifluoracetone in xylene. Neptunium (237) is separated free from other alpha emitters and from non-radioactive interferences, and the method may be readily adapted to remote control. [From Abstract]
Date: July 10, 1951
Creator: Moore, Fletcher L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Project Quarterly Progress Report [for] Period Ending May 15, 1951

Description: Technical report outlining the reconstitution of the Homogeneous Reactor Experiment Project (HRE) as the Homogeneous Reactor Project. Report covers the need for a broader developmental program to establish the feasibility of obtaining the potential advantages of homogeneous reactors for the production of fissionable materials and power. Details the ultimate objective of the ORNL program to provide the technical information required to determine the feasibility of a full scale plutonium power pr… more
Date: October 10, 1951
Creator: Swartout, J. A.; Secoy, C. H. & Winters, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemistry Division Quarterly Progress Report for Period Ending March 31, 1951

Description: Quarterly technical report including reports on chemistry of source, fissionable, and structural elements, nuclear chemistry, radio-organic chemistry, chemistry of separations processes, chemical physics, radiation chemistry, and instrumentation. [From Abstract]
Date: May 10, 1951
Creator: Lind, S. C.; Boyd, G. E. & Bredig, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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In-Pile Radiation Corrosion Experiments with Zirconium, Titanium, and Steel Alloys in 0.17 m UO2SO4 Solutions at 280°C

Description: In-pile loop experiments L-2-15 and L-4-16 were two of a series designed to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various conditions of radiation intensities, temperatures, solution compositions, and velocity flow past specimens.
Date: June 10, 1963
Creator: Jenks, G. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Project Progress Report: May-October 1959

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: February 10, 1960
Creator: Briggs, R. B.; Beall, S. E.; Lyon, R. N.; Bohlmann, E. G.; Ferguson, D. E.; McDuffie, H. F. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Homogeneous Reactor Project Quarterly Progress Report: May-July 1957

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: October 10, 1957
Creator: Briggs, R. B.; Winters, C. E.; Beall, S. E.; Lane, J. A.; Bohlmann, E. G.; Ferguson, D. E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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