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Experimental and Analytical Study of the Sputtering Phenomena

Description: An experimental apparatus was constructed to examine the heat-transfer characteristics of a sputtering front. In the present study, a heat source of sufficient intensity was located immediately below the sputtering front, which prevented its downward progress, thus permitting detailed measurements of steady-state surface temperatures throughout a sputtering front. A two-dimensional analytical model was developed to describe a stationary sputtering front where the wet-dry interface corresponds t… more
Date: March 1976
Creator: Howard, Paul A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Light-Water-Reactor Safety Research Program

Description: Report of a long-term program for monitoring the irradiation behavior of the materials in service in the primary-system sodium and the neutron shield of the EBR-11 sodium-cooled fast breeder reactor.
Date: 1977?
Creator: Argonne National Laboratory
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Light-Water-Reactor Safety Research Program

Description: Progress report on water-reactor-safety heat-transfer and flow problems. Covering the following research and development areas: loss-of-coolant accident research, transient fuel response and fission-product release program, mechanical properties of zircaloy containing oxygen, and steam-expulsion studies.
Date: December 1976
Creator: Argonne National Laboratory
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Light-Water-Reactor Safety Research Program

Description: This progress report summarizes the Argonne National Laboratory work performed during April, May, and June 1976 on water-reactor-safety heat-transfer and flow problems. The following research and development areas are covered: (1) Loss of coolant Accident Research: Heat Transfer and Fluid Dynamics; (2) Transient Fuel Response and Fission-product Release Program; (3) Mechanical Properties of Zircaloy Containing Oxygen; and (4) Steam-explosion Studies.
Date: 1976?
Creator: Argonne National Laboratory
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mechanical and Thermal Problems of Water-Cooled Nuclear Power Reactors

Description: "Some of the principal problems faced in the mechanical and thermal design of the Shipping port Pressurized Water Reactor core are discussed. The interplay of these problems with the requirements of other technologies is discussed, and areas which need more work are outlined."
Date: unknown
Creator: Palladino, N. J. & Sherman, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fabrication of a non-fertile fuel for the disposition of weapons plutonium in water reactors

Description: The feasibility of fabricating a non-fertile fuel containing weapons plutonium was evaluated. A surrogate fuel, specifically a CeO{sub 2}-ZrO{sub 2}-CaO fuel pellet, was fabricated using the solid-state reaction method to determine the effect of powder comminution, pellet formation, and sintering conditions on the microstructural development of the fuel. Dry ball milling of the precursor powders (CeO{sub 2}, ZrO{sub 2}, and CaO) proved to be an ineffective method for producing reactive powders … more
Date: March 1, 1996
Creator: Ramsey, K. B. & Blair, H. T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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One-way implodable tag capsule with hemispherical beaded end cap for LWR fuel manufacturing

Description: A capsule is described containing a tag gas in a zircaloy body portion having a hemispherical top curved toward the bottom of the body portion. The hemispherical top has a rupturable portion upon exposure to elevated gas pressure and the capsule is positioned within a fuel element in a nuclear reactor.
Date: December 1, 1997
Creator: Gross, Kenny & Lambert, John
Item Type: Refine your search to only Patent
Partner: UNT Libraries Government Documents Department
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Critical heat flux experiments in a circular tube with heavy water and light water.

Description: Experiments were performed to establish the critical heat flux (CHF) characteristics of heavy water and light water. Testing was performed with the up-flow of heavy and of light water within a 0.3744 inch inside diameter circular tube with 72.3 inches of heated length. Comparisons were made between heavy water and light water critical heat flux levels for the same local equilibrium quality at CHF, operating pressure, and nominal mass velocity. Results showed that heavy water CHF values were, on… more
Date: May 1980
Creator: Williams, C. L. & Beus, S. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Occurrence of Critical Heat Flux During Blowdown with Flow Reversal

Description: A small-scale experiment using Freon-11 at 130 degrees F (54.4 degrees C) and 65 psia (0.45 MPa) in a well-instrumented, transparent annular test section was used to study the occurrence of critical heat flux (CHF) during blow-down with flow reversal. The inner stainless steel tube of the annulus was uniformly heated over its 61-cm length. Inlet and exit void fractions were measured by a capacitance technique. Flow-regime transition was observed with high-speed photography. A 1-hr contact time… more
Date: January 1977
Creator: Leung, J. C. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Systematic Approach for the Evaluation of Technology Opportunities to Enhance the Proliferation Resistance of Civilian Nuclear Energy Systems

Description: Enhancing the proliferation resistance of nuclear energy systems and fuel cycles is an ambitious undertaking. Current systems, dominated by the light water reactor fuel cycle are quite proliferation resistant. However, continued accumulations of plutonium in spent fuel and accumulations of separated plutonium resulting from reprocessing are eroding the proliferation resistance of today's nuclear energy systems. Alternatives to address these issues invariably involve making trade-offs among diff… more
Date: March 10, 2003
Creator: Hassberger, J
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Oak Ridge Static Autoclave Water Decomposition Test

Description: Abstract: "Steady states decomposition product partial pressures of water exposed to an epithermal neutron flux of about 2 x 10-11, at 235F, were 0.4 to 0.65 psi. Recombination studies were made by adding hydrogen and oxygen gases to water under irradiation at different temperature and flux levels. The data show a significant effect of temperature on the rate of pressure drop of the added hydrogen and oxygen. In operating at two flux levels, 1.2 x 10-11 and 2.0 x 10-11, no difference in the rat… more
Date: May 1, 1951
Creator: Humphreys, J. R., Jr.; Abers, E. L. & Brown, P. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Report July, August, and September 1953

Description: This quarterly report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses water cooled reactors, liquid metal cooled reactors, reactor development metallurgy, basic metallurgy, applied metallurgy, and aqueous corrosion,
Date: September 30, 1953
Creator: Foote, Frank G. (Frank Gale), 1906- & Schumar, James F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Light-Water-Reactor Safety Research Program Quarterly Progress Report: October-December 1976

Description: Quarterly progress report summarizing work performed by the Argonne National Laboratory Light-Water-Reactor Safety Research Program. It includes sections discussing research and development in: (1) loss of-coolant accident research: heat transfer and fluid dynamics; (2) transient fuel response and fission-product release program; (3) mechanical properties of zircaloy containing oxygen; and (4) steam-explosion studies.
Date: March 1977
Creator: Sachs, Robert G. & Kyger, Jack A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Light-Water-Reactor Fission-Product Data Assessment

Description: This assessment seeks (1) to determine the most probable chemical compounds formed between fission products and actinides in urania fuels under normal and accident conditions and (2) to identify gaps in knowledge of these fission-product compounds. The ultimate goal of this effort is to develop predictive capability about the behavior of fission products under normal and accident conditions. The relevant thermochemical data have been organized by compound type, the chemical stability of resulta… more
Date: September 1982
Creator: Blackburn, P. E. & Johnson, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Light-Water-Reactor Safety Research Program Quarterly Progress Report: July-September 1977

Description: Quarterly report summarizing research and development on water-reactor-safety heat-transfer and flow problems, including: Loss-of-coolant accident research, transient fuel response and fission-product release, mechanical properties of zircaloy containing oxygen, and steam-explosion studies.
Date: January 1978
Creator: Argonne National Laboratory
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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