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U-10 Wt % Mo Fuel Element: Irradiation in SRE

Description: From abstract: The fuel element assembly was successfully irradiated in the SRE to a maximum burnup of 5300 Mwd/MTU, at a peak fission rate of approximately 1.5 x 10E13 fissions/cm3-sec and a maximum central temperature near 1200F.
Date: August 31, 1965
Creator: Arnold, J. L.; Miller, K. J. & Peterson, R. M.
Partner: UNT Libraries Government Documents Department
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Gas-Phase Radiolysis of Propane

Description: Abstract. the direct and inert-gas radiolysis, as well as the vacuum ultra-violet photolysis of CD3CH2CD3, CH3CD2CH3 and C3H2+C3D3 mixtures have been investigated in the presence of radical scavengers. The major conclusions are : (a) at atmospheric pressures, neutral propane decomposition contributes to the observed products although to a lesser extent than parent ion decompositions ; (b) a variation in pressure has a pronounced effect on the fragmentation of the parent ion ; (c) the hydrogen a… more
Date: May 31, 1963
Creator: Ausloos, Pierre J.; Lias, Sharon G., 1935- & Sandoval, L. B., (Mrs.)
Partner: UNT Libraries Government Documents Department
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The Study of the Potential Applications of Radioisotope Technology to Water Resource Investigations and Utilization

Description: The study which has been carried out under Contract AT(30-1)2477 has as its objective the review of all work which has been done on the application of radionuclear techniques to research in water resources and supply, the evaluation of this work, and the suggestions of specific experiments which must be performed if these applications are to be extended.
Date: January 31, 1961
Creator: Feely, Herbert W., 1928-
Partner: UNT Libraries Government Documents Department
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Fifth Quarterly Progress Report on Fission Product Applications Using Gaseous Beta Sources

Description: "Rates of acetylene polymerization induced by Kr/sup 85/ in d-c fields were up to 15 times greater than those observed when no fields were imposed. Work to determine the relations between acetylene pressure, Kr/sup 85/ concentration, and the field intensity is continuing. In other activities, equipment is being designed to study the effects of megacycle electric fields on radioinduced chemical reactions."
Date: October 31, 1961
Creator: Graessley, William W. & Zufall, John W.
Partner: UNT Libraries Government Documents Department
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The High-Temperature Irradiation Behavior of Hypostoichiometric Uranium Monocarbide

Description: From abstract: A series of three multi-compartmented experiments was designed to investigate the irradiation behavior uranium carbide fuels, as a function of composition, temperature, and burn-up; and the mechanical properties of Type 304 stainless steel, as a function of temperature and integrated thermal neutron flux.
Date: August 31, 1965
Creator: Hahn, R. D.
Partner: UNT Libraries Government Documents Department
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Technical and economic potentials of shale oil production by nuclear explosives

Description: "In the following report, a new technology is discussed which was first proposed in 1959, but which has been developed mainly since 1964; the in situ production of oil from shale by large underground retorts created by nuclear explosives. The first part of the present report describes this new process; the second part gives an analysis of the United States and the world endowments with crude oil resources and oil shale deposits and finally, the third part deals with expected cost estimates of t… more
Date: August 31, 1967
Creator: Heiss, Klaus-Peter
Partner: UNT Libraries Government Documents Department
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Synthesis of Semiconductor Materials by Radiation Induced Reations

Description: "Progress is reported on: design of a continuous flow system for the irradiation of silane using a Cos5 source; pile irradiation of silane samples at elevated temperatures; investigation of materials other than silane, including nonsilicon compounds as well as those containing the silyl group; modification of the existing vacuum system for handling larger quantities of silane as well as increasing the accuracy of the pressure measurements; and use of an electric discharge for the decomposition … more
Date: October 31, 1961
Creator: Held, Kelman & Goldman, Richard
Partner: UNT Libraries Government Documents Department
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Final Contract Report for September 1, 1959 to August 31, 1960 .

Description: "As presented in the original proposal the project consisted essentially of three parts: Phase I, Development and refinement of a radiochemical flow counting technique for the study of kinetics of reactions in solution ; Phase II, The application of this technique to the detailed study of the mechanism of solvolysis of sulfonium salts in mixed solvents ; Phase II, The further application of this kinetic technique, as a longer term aim, to other reacting systems of biochemical or other interest.… more
Date: October 31, 1961
Creator: Hyne, James B.; Abrell, J. W.; Gurst, J. E. & Jacobson, Ada L.
Partner: UNT Libraries Government Documents Department
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Pebble Bed Friction Factor and Thermal Expansion Tests

Description: Tests were conducted to determine the friction factor of randomly packed beds of 3/4-inch diameter spheres in 8-inch and 15-1/4-inch diameter beds, and of 1-1/2-inch diameter spheres in 15-1/4-inch diameter bed. The bed depths were varied in an attempt to isolate the effects of entrance and exit losses. The bed Reynolds number, base on sphere diameter, was varied from 5,000 to 50,000.
Date: August 31, 1960
Creator: Leeman, C. A.
Partner: UNT Libraries Government Documents Department
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Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Fourth Quarterly Report, July-September 1962

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: January 31, 1963
Creator: Leitz, F. J.
Partner: UNT Libraries Government Documents Department
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Investigations of Radioactive Fuel-Bearing Glasses

Description: "A series of glass compositions containing uranium oxide was investigated to determine fiberizability and physical properties of resultant fibers. The basic properties to be determined were the maximum U/sub 3/O/sub 8/ content in a fiberizable glass and the maximum service temperature of the fibers. Glasses containing 60 wt% U/sub 3/O/sib 8/ were fiberizable; the fibers had strengths of 100,000 psi at 1600 deg F. Fiber-forming equipment was installed at Moun Laboratory to produce glass fibers c… more
Date: July 31, 1961
Creator: Lockwood, P. A.
Partner: UNT Libraries Government Documents Department
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High Energy Storage Ceramic Capacitor. Quarterly Report No. 4 [for] August 19, 1957 -- December 31, 1957

Description: The chief purpose of this contract is the development of ceramic materials with high dielectric constant and high dielectric strength values, and suitable for use of dielectrics in capacitors capable of storing large amounts of energy in small volumes. Work performed during the fourth quarter included (1) Material development and sample preparation; (2) Sample testing; (3) discussion of ceramic density measurements; (4) Optical studies of titanates; (5) Fabrication of large ceramics; and (6) Ca… more
Date: October 31, 1960
Creator: Lupfer, D. A.
Partner: UNT Libraries Government Documents Department
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High Energy Storage Ceramic Capacitor. Quarterly Report No. 5 [for] January 1, 1958 -- March 31, 1958

Description: The chief purpose of this contract is the development of ceramic materials with high dielectric constant and high dielectric strength values, and suitable for use of dielectrics in capacitors capable of storing large amounts of energy in small volumes. Work performed during the fifth quarter included (1) Material development and sample preparation; (2) Sample testing; (3) Optical studies of titanates; (4) Fabrication of large ceramics; and (5) Capacitor design.
Date: October 31, 1960
Creator: Lupfer, D. A.
Partner: UNT Libraries Government Documents Department
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Adsorption of Radioactive Gases on Activated Carbon

Description: The purpose of this experiment is to study the quantitative adsorption characteristics of a carbon adsorber bed receiving a radioactive inert gas in a helium stream. An objective of the experiment is to measure the equilibrium transmission of the radio-active gas through a carbon adsorber in order to determine if radio-active decay of the adsorbed gas permits additional adsorption.
Date: August 31, 1960
Creator: Madey, Richard; Barker, J. J.; Beebe, M. R. & Stephenson, T. E.
Partner: UNT Libraries Government Documents Department
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Startup Testing of the PM-2A Nuclear Power Plant

Description: Abstract: A detailed description of the PM-2A reactor, primary system and instrumentation is presented. A general description of the secondary system and plant arrangement at Camp Century, Greenland is included. The results of the startup physics, shielding, thermal and hydraulics and radiochemistry test are presented. the analysis performed on the shielding and thermal and hydraulic tests is included. The shielding problem at startup and the shielding modification made to the plant are describ… more
Date: March 31, 1962
Creator: McCool, W. J.; Ryan, R. M.; Richards, W. M. S.; Bradley, P. L.; Stephenson, L. D. & Cox, J. F.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Project. Internal Steam Separation Development of Radial Vane Steam Separators

Description: This technical report describes the development, design, operation, and performance of a full-circle, radial-vane steam separator for the boiling water section of a nuclear superheat reactor. Steam-water tests of this model have demonstrated that is has vane capacity in excess of that required for the 300-Mx(e) separate superheat reactor and for the 300-Mw mixed spectrum superheat reactor. It is proposed that the vane capacity requirement of the 600 Mw(e) separate superheat reactor may be atta… more
Date: May 31, 1963
Creator: Moen, R. H.
Partner: UNT Libraries Government Documents Department
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