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Effect of Reactor Irradiation on the Thermal Conductivity of Uranium Impregnated Graphite at Elevated Temperatures

Description: "An experiment to determine the effect of reactor irradiation on the thermal conductivity of uranium-impregnated graphite at elevated temperatures as described. The results show a decrease in the thermal conductivity saturating at [approximately] 60 percent at a temperature of 700 degrees C; at [approximately] 50 percent at a temperature of 1000 degrees C; and at [approximately] 25 percent at a temperature of 1300 degrees C. It was found that after irradiation at a given temperature, exposure… more
Date: April 29, 1954
Creator: Durand, Richard E.; Klein, David J. & Nykiel, Harry H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sodium Graphite Reactor, Quarterly Progress Report, June-August 1953

Description: "Engineering was continued on the development of sodium cooled, graphite moderated type reactors. General studies were carried out as well as studies specifically devoted to the following: a. full scale poser-only plant, b. thirty-mega watt pilot plant, the SGR, c. sodium reactor experiment, the SRE. This work consisted of theoretical analysis of various aspects of nuclear performance; economic investigations of different fuel element, cooling system and plant arrangements; and experimental i… more
Date: January 20, 1954
Creator: Inman, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Physics, Quarterly Progress Report, November, 1953 - January 1954

Description: "A series of thermal neutron diffusion length measurements has been made on non-multiplying lattice of lead-cadmium alloy rods in D2O. One-inch diameter rods in square lattice spacing of 4, 9, 6, 9, and 12 inches were used. Excellent agreement was found between theoretical and experimental values of the diffusion length. The analysis o the diffusion length measurement required a correction for the epithermal neutrons entering the exponential tank. These epithermal neutrons provided a distri… more
Date: May 15, 1954
Creator: Laubenstein, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Separations Chemistry, Quarterly Progress Report, October-December 1953

Description: "Work has continued on high temperature methods for processing irradiated uranium fuel. Additional results have been obtained with fused halide treatment, solid scavengers and direct Pu distillation. With fussed fluorides about 95 per cent of the Pu was removed from a uranium sample, while treatment of uranium with HC1 gas removed almost all the Pu and many fission products. treatment of molten uranium with uranium oxide removed a substantial fraction of the fission products without removing P… more
Date: March 26, 1954
Creator: Motta, E. E.; Bareis, D. W. & Cubicciotti, D. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Role of Ionization in Radiation Annealing

Description: "The role of ionization in the phenomenon of 'radiation annealing' of graphite has been studied by using a 1-Mev electron beam. Changes in the c-axis of a sample with a Hanford irradiation of 460 mwd/ct were studied. Two thermal anneals of 4 hours each at 350 degrees C proved sufficient to complete the thermal annealing at this temperature. The samples were then irradiated for 7-1/2 hours at a temperature of 340 degrees C. The samples received an irradiation of 47 microampere-hours, equivale… more
Date: unknown
Creator: McClelland, J. D.; Smith, A. W. & Senkovits, E. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Sodium Cooled, Graphite Moderated, Low Enrichment Uranium Reactor for the Production of Useful Power

Description: "A design study is presented for a sodium cooked, graphite moderated power reactor utilizing low enrichment uranium fuel. The design is characterized by dependence on existing technology and the use of standard, or nearly standard, components. The reactor has a nominal rating of 167 thermal megawatts, and a plant comprising three such reactors for a total output of 500 thermal megawatts is described. Sodium in a secondary, non-radioactive, circulation system carries the heat to a steam genera… more
Date: September 15, 1954
Creator: Weisner, Edward F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Chemical Effects of 1 Mev Electrons on BrF3 at 25 degrees C

Description: "An investigation of the chemical effects of 1-Mev electrons on BrF3 at 25 degrees C has been carried out. Pressure measurements taken during the irradiation suggest the presence of Br2 and BrF5 as decomposition products and a fractional distillation of the irradiated liquid confirmed their presence. The extent of decomposition was determined both by fraction distillation and spectrophotometric methods. The radiation effect seemed to reach saturation when approximately 10 per cent of the BrF3… more
Date: October 1, 1954
Creator: Yosim, S. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Sodium Graphite Reactor, Quarterly Progress Report, March-June 1954

Description: "The Atomic energy Commission has undertaken a development program to provide the technology needed for the evaluation and economic design of nuclear power plants. This program is to be carried out during the next five years at several national laboratories and industrial organizations. The Sodium Graphite Reactor (the SGR) is one of those to be investigated and experimentally tested as part of this 5-year effort. The program on the SGR is intended to expand our area of information coverin… more
Date: September 1, 1954
Creator: Siegel, Sidney & Inman, Guy M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Separations Chemistry, Quarterly Progress Report, April-June 1954

Description: "Scale-up experiments on high temperature fuel recovery processes have included the dummy run phase on the handling of 1-kologram samples of molten, non-irradiated uranium in the hot cell. The next step involves the use of spent X-10 fuel slugs. Small scale experiments with X-10 uranium on the extaction of Pu with Mg show that as much as 80 per cent of the Pu can be removed in pone pass. Treatment of uranium with fused fluorides can remove at least 90 per cent of the Pu in one pass. Oxide sc… more
Date: unknown
Creator: Bareis, David W.; Cubicciotti, Daniel D. & Motta, E. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Device for Continuous Detection of Hydrogen in Sodium

Description: Abstract: A device to detect the presence of hydrogen in sodium has been developed. Such a device, installed in a sodium heated steam generator, would signal the presence of water in the sodium resulting from a leak in the sodium-water barrier.
Date: December 15, 1960
Creator: Strahl, H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermodynamic Diagrams for Sodium

Description: From abstract: This paper presents temperature-entropy and Mollier charts for sodium, and describes briefly the method used for their construction, based upon data from the literature.
Date: July 13, 1950
Creator: Inatomi, T. H. & Parrish, W. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Conceptual Design of a Thorium-Uranium (233) Power Breeder Reactor

Description: From abstract: A conceptual design study has been performed for a sodium cooled, graphite moderated, thermal power-breeder reactor utilizing the Thorium-Uranium 233 breeding cycle. Several aspects of the design of the system are considered but no attempt has been made to supply all the details. It appears that the design presented is feasible and will allow the production of economic power as well as full utilization of thorium resources.
Date: February 1, 1954
Creator: Henrie, J. O. & Weisner, E. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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