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Analysis of Thorex Pilot Plant Radiation Exposures During 1955

Description: The Thorex Pilot Plant at Oak Ridge National Laboratory was operated during 1955, processing reactor-irradiated thorium slugs to recover U233 and thorium and 12 MTR fuel elements to recover U235 and Np237. The radiation exposure received by operating personnel during this period averaged 60 mrcp/man-week. Most radiation exposure was received in areas that were intended to be only slightly or nonradioactive. However, because insufficient decontamination of process solutions was achieved and equiā€¦ more
Date: November 16, 1956
Creator: McCarley W. T.
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Automatic Isotope Mass Spectrometer : Job Specification JS-741, Rev. 2

Description: The following document analyzes the Automatic Isotope Mass Spectrometer that consists of a Laboratory Isotope Mass Spectrometer, covered by Union Carbide Nuclear Company Job Specification "JS-747", which has been modified to meet Union Carbide Nuclear Company Job Specification "JS-741", as well as the instrument's samples collected and analyzed.
Date: September 16, 1955
Creator: Union Carbide Nuclear Company
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Bismuth Casting and Canning : (Information Report)

Description: Introduction: The experimental work at Mound Laboratory on bismuth casting and the sealing of aluminum irradiation containers is an outgrowth of the bismuth recovery project. Since the recovered bismuth contains residual activity it is necessary that the bismuth be processed to the point that no contamination will result from shipment or any subsequent operations required to prepare the bismuth for irradiation. In order to satisfy these requirements the work here has consisted of investigating ā€¦ more
Date: June 16, 1952
Creator: Engle, Paul
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A Catalog of Fallout Patterns

Description: Abstract: In the event of a massive nuclear attack, the combined fallout from quantities of surface-burst nuclear weapons must be considered as a serious hazard over an extended area. This report presents one method for rapidly estimating the fallout from such an attack.
Date: April 16, 1956
Creator: Greenfield, S. M.; Rapp, R. R. & Walters, P. A.
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A Description of the Acetone-Dye Solution Method of Demarcating a Leak Process Tubing While in the Pile

Description: Abstract: "A method has been devised and successfully used for marking a leaking pile process tube prior to its removal from the pile, such that subsequent location of the leak is more easily accomplished. An acetone solution of Testor's Dark Red Airplane Dope is poured into the suspect tube. The solution leaks from the hole and stains the surrounding area a light pink. To date the method has been used on tubes 3573F, 0486F, 0867F, and 3670F."
Date: July 16, 1952
Creator: DeHollander, W. R.
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Discussion with WAPD Personnel Regarding Oxide Fuel Materials

Description: R. H. Fillnow and H. Pennington of WAPD visited HAPO on September 14-15, 1955, to discuss HAPO special irradiation facilities and review fuel element problems with HAPO personnel. During their meeting with Metallurgy Research personnel, the progress of the evaluation of UOā‚‚ elements for the PWR and the results of recent HAPO irradiations of oxide type fuel elements were discussed. Although brief, this information exchange was particularly valuable as many of the problems associated with the appā€¦ more
Date: September 16, 1955
Creator: Sanderson, M. J.
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Effect of Boron Liner on Neutron Background in Cavity

Description: Introduction: "In connection with conducting neutron experiments in a pit with earth and concrete walls, it was proposed that the background flux of neutrons might be reduced by lining the walls of the pit with a neutron absorber such as boron. To determine how much liner material would be desirable and what diminution in the neutron background could be expected, the following measurements were undertaken."
Date: January 16, 1953
Creator: Benveniste, Jack
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Effect of Neutron Interaction on Criticality

Description: A general method is developed to allow calculation of the critical buckling of an assemblage of fissile regions coupled by neutron leakage. Consideration is given both to regions embedded in vacuum and in material media. Several cases of simple geometry are further developed to illustrate the theory.
Date: January 16, 1956
Creator: Stuart, G. W.
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Exponential Pile Measurements in Water Moderated Lattices with Enriched Uranium Rods

Description: This paper presents the results of a series of buckling measurements involving the use of enriched uranium rods (1.007% by weight UĀ²Ā³āµ) in light water. The effect of replacing a water reflector with one of uranyl nitrate solution of two different concentrations, 536 and 188 grams of U per liter of solution was investigated for the 0.925" rods with the 1.74 Hā‚‚O/U-volume ratio in the core. Some information was also obtained on the extrapolation length to be used in unreflected cases. The applicatā€¦ more
Date: January 16, 1956
Creator: Clayton, E. D. & Neumann, H.
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The Fabrication of Subassemblies for the Supercritical-Water Reactor

Description: In studies of the fabrication of fuel subassemblies for the supercritical-water reactor, the limited ductility of stainless steel-UOā‚‚ fuel sheet made the fabrication of corrugated-flat-plate-type subassemblies impractical. A fabricable MTR-type assembly, 5/8 in. square and 30 in. long, was developed. Methods for edge cladding fuel sheet were developed and a brazing alloy, GE-75, was found to be corrosion resistant in supercritical water.
Date: August 16, 1954
Creator: Keeler, J. R. & Hare, Alan W.
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The Fabrication of Thorium Tubes

Description: Abstract: "Thorium tubes were cold drawn from extruded tube stock and also from drilled hot-rolled rod. Total reductions up to approximately 85 per cent were accomplished by conventional tube-drawing methods, without an intermediate anneal. The hard-drawn tubes had high tensile strength, but the ductility, as indicated by flaring and flattening tests, was low."
Date: January 16, 1953
Creator: Saller, Henry A. & Keeler, J. R.
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Feasibility Report: Measurement of Stainless Steel Corrosion Rates by Activation Analysis

Description: Relations governing the measurement of Stainless Steel corrosion rates by activation analysis are derived and discussed. The principal neutron induced radioactivities are calculated and graphed. Shielding requirements are considered and it is concluded that six inches of lead shielding should be sufficient for the proposed experiments if the samples are allowed to cool for one day in the reactor storage basin.
Date: September 16, 1955
Creator: Cadwell, J. J.
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The Fission Cross Section f Factor of PuĀ²Ā³ā¹

Description: A presentation of the values for the PuĀ²Ā³ā¹ fission cross section f factor extended into a higher energy range than previously reported in BNL-250. The values were obtained by integrating the standard expression defining the f factor on the Hanford IBM-CPC equipment. The un-fit experimental data of Leonard, as corrected for resolution and doppler effect, was used above 0.03 ev being attached to an analytic fit applicable below this point. Results are shown on the accompanying graph.
Date: December 16, 1954
Creator: Stuart, G. W.
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Geology and Ore Deposits of Mesa V, Lukachukai District, Arizona

Description: From abstract: Mesa V of the Lukachukai area is capped by Morrison sediments which dip gently eastward from the mountains to the mesa tip, where the strata are tilted sharply to the opposite dip by the Lukachukai monocline. The Salt Wash of Mesa V contains ore outcrops which indicate favorable intensity of mineralization at one horizon along a 2000-foot outcrop interval. Other scatted exposures indicate the existence of ore under much of the mesa surface.
Date: November 16, 1951
Creator: King, John W.
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