Reclamation of Contaminated Kinney and Diffusion Pump Oils and Removal of Uranium Therefrom (open access)

Reclamation of Contaminated Kinney and Diffusion Pump Oils and Removal of Uranium Therefrom

Abstract: Test distillations were made with Kinney and diffusion pump oils under vacuum in order to determine accurately the temperature range over which satisfactory distillate may be collected. Also recommendations are made as to the most advisable type of heating equipment necessary to produce the required heat and maintain the desired temperature. In addition, several important refinements in the distillation equipment were checked for operational characteristics and for their efficiency in aiding the production of uranium-free distillates.
Date: March 10, 1947
Creator: Lee, J. E. Jr.; Aikin, L. M. & Susano, C. D.
System: The UNT Digital Library
Preparation of Ductile Zirconium: Progress Report for February 1950 (open access)

Preparation of Ductile Zirconium: Progress Report for February 1950

Abstract: A tungsten tipped electrode has been used in the continuous casting arc furnace for a 25 minute period during which a 12 inch length of ingot was made. Thermocouple junctions within the mold wall have been improved to give mold zone temperature. A total of 10 iodide dissociation runs have been conducted using feed rates of .62-22.7 lbs ZrI₄ per hour with attendant conversion efficiencies of 97.7-16.4% and zirconium yields of 255-41.2 grams per hour. A curve expressing these data for an arbitrarily selected set of conditions is presented.
Date: March 10, 1950
Creator: DiPietro, W. O.; Findlay, G. R. & Moore, J. H.
System: The UNT Digital Library
Geology of the Poison Canyon Mine, Valencia County : Sec. 19, T. 13N., R. 9W., near Grants, New Mexico (open access)

Geology of the Poison Canyon Mine, Valencia County : Sec. 19, T. 13N., R. 9W., near Grants, New Mexico

This report deals with the uranium deposits at the Poison Canyon mine
Date: March 10, 1953
Creator: Mathewson, Donald E.
System: The UNT Digital Library
SM-1 (APPR-1) Research and Development Program : Final Report on Short-Lived and Fission Product Activity in the SM-1 Primary Coolant, Task III (open access)

SM-1 (APPR-1) Research and Development Program : Final Report on Short-Lived and Fission Product Activity in the SM-1 Primary Coolant, Task III

Abstract: The primary coolant of the SM-1 (APPR-1) was analyzed for short-lived and fission product activities. Manganese-56 was found to be the predominant non-fission product nuclide contributing to the short lived activity. Fission products were found in the coolant. It is concluded these fission products originate from a defects in the cladding and from surface contamination of the fuel elements.
Date: March 10, 1959
Creator: Brown, William S. & Hasse, Robert A.
System: The UNT Digital Library
Design and Economic Evaluation of Mobile Blankets for Fast Reactors (open access)

Design and Economic Evaluation of Mobile Blankets for Fast Reactors

Report evaluating the design characteristics and limitations of mobile blankets for breeder reactors. This also includes economic considerations for each tested blanket. Appendices begin on page 40.
Date: March 10, 1964
Creator: Klickman, A. E.; Ball, G. L.; Edwards, J. J.; Jens, W. H.; Segal, B. M.; Amorosi, A. et al.
System: The UNT Digital Library