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The Absorption and Translocation of Several Fission Elements by Russian Thistle

Description: Abstract: An investigation was conducted to determine the absorption and translocation of fission products by Russian thistle from a localized spot of contaminated soil. The amount and identity of the radioactive elements absorbed and translocated by the Russian thistle is given along with the location of these elements in the plants. Beta radioactivity to the amounts of 10 microcuries per gram caused no visible effects on the growth habits of sectioned material are included.
Date: June 8, 1950
Creator: Selders, A. A.
Item Type: Refine your search to only Report
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The Action of Oxygen on Activated Charcoal

Description: The following report provides information conducted with the purpose of ascertaining the effect of oxygen on activated charcoal at approximately one atmosphere by measuring the amount of CO2 formed over a known length of time.
Date: June 29, 1951
Creator: Bigelow, J. E.; Belaga, M. W. & Mulvihill, R. J.
Item Type: Refine your search to only Report
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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending March 10, 1956

Description: This quarterly progress report of the Aircraft Nuclear Propulsion Project at ORNL records the technical progress of the research on circulating-fuel reactors and ether ANP research at the Laboratory under its Contract W-7405-eng-26. The report is divided into three major parts: I. Reactor Theory, Component Development, and Construction, II. Materials Research, and III. Shielding Research.
Date: June 13, 1956
Creator: Jordan, W. H.; Cromer, S. J. & Miller, A. J.
Item Type: Refine your search to only Report
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Alkali Metal Physical Properties Program at Pratt & Whitney Aircraft-CANEL

Description: The favorable combination of physical properties such as heat capacity, viscosity, electrical resistivity, thermal conductivity and high temperature liquid range make alkali metals, in principle, among the best heat transfer fluids available for use in nuclear reactor and other esoteric powerplant systems. Unfortunately, many of these properties are not known with sufficient certainty in the high temperature region to permit optimization of design criteria for developing maximum efficiency coo… more
Date: June 15, 1962
Creator: Kapelner, S. M. & Cleary, Robert E., 1920-
Item Type: Refine your search to only Report
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Alloys of Uranium with Zirconium, Chromium, Columbium, Vanadium, and Molybdenum

Description: Abstract: Information on five uranium binary alloy systems has been surveyed. These systems are the alloys of uranium with zirconium, chromium, columbium, vanadium, and molybdenum. The equilibrium diagrams are discussed, and where available, data have been included on diffusion studies, cladding experiments, and mechanical properties.
Date: June 19, 1952
Creator: Saller, Henry A. & Rough, Frank A.
Item Type: Refine your search to only Report
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The Ammonium Carbonate Pressure Leaching of Uranium Ores Proposed as Feed to the Pilot Plant at Grand Junction, Colorado : Progress Report

Description: From introduction: This is Progress report BMI-282, the first of a series covering the operation of the pressure-leaching towers for the extraction of uranium by an ammonium carbonate leach...This report discusses the data obtained from tests run to show the effects of such variables as the amount of air and carbon dioxide passed through the pulp, temperature, pressure, and concentration of ammonium carbonate and ammonium bicarbonate in the leach solution on the extraction of uranium.
Date: June 15, 1955
Creator: Wheeler, C. M.; Langston, B. G. & Stephens, F. M., Jr.
Item Type: Refine your search to only Report
open access

Analyses of Decay Curves of Irradiated Plastics

Description: The following report covers the results of a general program that was conducted at the Oak Ridge National Laboratory to investigate the effects on plastic materials of exposure to radiation in the pile. In the investigation, several plastics were irradiated, and on removal from the pile, their rates of decay were determined by measurement of gamma activity in an ionization chamber.
Date: June 22, 1949
Creator: Saleeby, R. N.; Cheshire, J. R. & Jensen, W. P.
Item Type: Refine your search to only Report
open access

Analysis of Uranium-Nicked Alloys

Description: Abstract. Methods for determination of both uranium and nickel in solutions of these metals are described. Alloys can be dissolved in nitric acid treated with citric acid to complex the uranium, and the nickel precipitated as nicked dimethylglyoxime. The uranium is reduced and titrated with standard ceric sulfate. These methods are for the determination of macro amounts of uranium and nickel with errors on the order of 0.1%.
Date: June 7, 1945
Creator: Ericson, R. P.
Item Type: Refine your search to only Report
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Application of Ascorbic Acid Method to Uranium in Salvage Solutions

Description: Abstract: The erroneously high values for uranium content of salvage solutions as determined by the ether extraction-ascorbic acid procedure have been demonstrated to be due to the presence of colored organic materials in these solutions. Evaporation of such solutions to fumes of HC104 before extraction has been shown to be completely successful in preventing such interference while pretreatment with activated carbon is sufficiently successful for application in Control laboratories. Complete … more
Date: June 11, 1947
Creator: Rothenberger, C. D. & Grimes, W. R.
Item Type: Refine your search to only Report
open access

Applications of Strain Cycling Considerations to Superheat Fuel Design

Description: A potential performance limitation of superheat fuel is the susceptibility of the fuel cladding to low cycle fatigue failure. Two simplified analytical methods are presented to estimate the cyclic lifetime of circular superheat fuel cladding. One failure relation is based on a displacement method. The other failure relation is based on a stress method. These relations were compared with data from the literature, and with data involving damage obtained by Reynolds. A recommended design procedur… more
Date: June 1963
Creator: Rieger, G. F.
Item Type: Refine your search to only Report
open access

Attritioning of Temple Mountain Ore

Description: Abstract: The results of both dry and wet attritioning of Temple Mountain ore are presented. In order to obtain effective attritioning on this ore, the amphaltite must be removed before attritioning. With the asphaltite present, dry attritioning causes a build-up of asphaltite on the surface of sand grains, with consequent loss of uranium values. In wet attritioning, the asphaltite is not broken down or attritioned, because of its low specific gravity and resilience.
Date: June 19, 1953
Creator: Butler, J. N.; Stephens, R. W. & Ehrlinger, H. P., III
Item Type: Refine your search to only Report
open access

Automatic Scanning And Measuring Of Bubble Chamber Photographs

Description: The development of high-energy charged particle accelerators such as the Bevatron and of improved nuclear-event detection devices such as the Berkeley 72-in. hydrogen bubble chamber has greatly increased the need for high-speed data reduction of nuclear events. Full exploitation of the potential of the 72-in. bubble chamber demands a very high-speed analysis system. This paper describes an approach to such a system.
Date: June 1, 1960
Creator: Grasselli, Antonio
Item Type: Refine your search to only Report
open access

Beta Magnet Current Stability

Description: Abstract: A TEC regulator amplifier driving an Eaterline-Angus recording meter was used to record magnet current variations. Tests were made to determine magnet current variations. Tests were made to determine magnet current stability for currents from 500 amperes to 4000 amperes. Changes were necessary in both the TEC and GE regulators before currents below 2500 amperes could be regulated. Regulation to 0.025 percent for and hour was obtained for currents of 1000 to 4000 amperes with the TEC a… more
Date: June 8, 1947
Creator: Hudson, E. D. & Becker, M. C.
Item Type: Refine your search to only Report
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