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Blanket technology experiments at Argonne National Laboratory

Description: Argonne National Laboratory has the largest US program for the development of blanket technology. The goals of the program are to resolve critical issues for different blanket concepts, to develop the understanding and predictive capability of blanket behavior, and to develop the technology needed to build and operate advanced fusion blankets. The projects within the program are liquid metal MHD, breeder neutronics, tritium oxidation, transient electromagnetics, FLIBE chemistry, and insulator c… more
Date: February 1, 1988
Creator: Mattas, R. F.; Reed, C. B.; Picologlou, B.; Finn, P.; Clemmer, R.; Porges, K. et al.
Partner: UNT Libraries Government Documents Department
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Potential of pyroprocessing for partitioning purex wastes

Description: The processes are extremely compact. The process reagents are highly resistant to radiation damage and, therefore, can be used to handle short-cooled, highly concentrated waste with negligible degradation. Most reagents can be recycled back through the process many times, thereby minimizing the generation of waste products, and also reducing the process cost. Fission-product wastes are discharged from the process as concentrated, solid wastes, typically in a metal matrix suitable for permanent … more
Date: July 23, 1980
Creator: Coops, M. S. & Sisson, D. H.
Partner: UNT Libraries Government Documents Department
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Prediction of electron beam welding spiking tendency

Description: On the basis of measured temperature distributions in electron beam welding cavities it is shown that the vapor pressure force dominates in the lower region and the surface tension in the upper region. The region where these two forces are approximately equal is unstable and the surface tension force causes inward flow of liquid metal which tends to form a projection. For a specific material this projection location was found to depend on cavity depth. By postulating that the formation of liqui… more
Date: February 1, 1978
Creator: Schauer, D. A. & Geidt, W. H.
Partner: UNT Libraries Government Documents Department
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Liquid metal requirements for inertial confinement fusion

Description: The lithium waterfall reactor is described as a concept in which liquid lithium serves as the coolant, tritium breeder, and 1st-wall and blanket structure protector. This reactor has emerged as a promising concept that alleviates the major problems associated with inertial confinement fusion systems. It eliminates the first wall problems resulting from x-rays and pellet debris, and minimizes cyclical thermal stresses. Also, the thick falling region of lithium attenuates neutrons to the point wh… more
Date: December 1, 1977
Creator: Meier, W. R. & Maniscalco, J. A.
Partner: UNT Libraries Government Documents Department
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Methodology for estimating sodium aerosol concentrations during breeder reactor fires

Description: We have devised and applied a methodology for estimating the concentration of aerosols released at building surfaces and monitored at other building surface points. We have used this methodology to make calculations that suggest, for one air-cooled breeder reactor design, cooling will not be compromised by severe liquid-metal fires.
Date: January 1, 1985
Creator: Fields, D. E. & Miller, C. W.
Partner: UNT Libraries Government Documents Department
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Study of grain boundary segregation using the Auger electron emission technique. Annual technical progress report, VIII, January 1-December 31, 1978

Description: The susceptibility of nickel-copper alloys to liquid metal embrittlement was studied by Auger spectroscopy. Alloys corresponding to Monel 400 with various levels of additional phosphorous were employed and were given various thermal treatments to control the extent of segregation. Segregation of phosphorous to the boundaries, with accompanying decreases in copper and nickel concentrations, greatly reduces susceptibility to intergranular embrittlement by mercury.
Date: January 1, 1978
Creator: Stein, D. F.; Heldt, L. A. & Funkenbusch, A. W.
Partner: UNT Libraries Government Documents Department
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Solar Central Receiver Hybrid Power Systems sodium-cooled receiver concept. Final report. Volume I. Executive summary

Description: The overall, long-term objective of the Solar Central Receiver Hybrid Power System program is to identify, characterize, and ultimately demonstrate the viability and cost effectiveness of solar/fossil, steam Rankine cycle, hybrid power systems that: (1) consist of a combined solar central receiver energy source and a nonsolar energy source at a single, common site, (2) may operate in the base, intermediate, and peaking capacity modes, (3) produce the rated output independent of variations in so… more
Date: January 1, 1980
Partner: UNT Libraries Government Documents Department
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Solar Central Receiver Hybrid Power Systems sodium-cooled receiver concept. Final report. Volume II, Book 2. Conceptual design, Sections 5 and 6

Description: The overall, long-term objective of the Solar Central Receiver Hybrid Power System program is to identify, characterize, and ultimately demonstrate the viability and cost effectiveness of solar/fossil, steam Rankine cycle, hybrid power systems that: (1) consist of a combined solar central receiver energy source and a nonsolar energy source at a single, common site, (2) may operate in the base, intermediate, and peaking capacity modes, (3) produce the rated output independent of variations in so… more
Date: January 1, 1980
Partner: UNT Libraries Government Documents Department
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Liquid-metal MHD flow in a duct whose cross section changes from a rectangle to a trapezoid, with applications in fusion blanket designs

Description: This paper treats the liquid-metal MHD flow in a semi-infinite rectangular duct and a semi-infinite trapezoidal duct, which are connected by a finite-length transition duct. There is a strong, transverse, uniform magnetic field. The walls parallel to the magnetic field (sides) remain parallel, while the walls intersecting the magnetic field are twisted in the transition duct to provide the change in cross sectional shape. The left side has a constant height, while the height of the right side i… more
Date: April 1, 1986
Creator: Walker, J.S.
Partner: UNT Libraries Government Documents Department
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Remote recovery of irradiated tensile samples incapsulated in Pb-Bi

Description: The Swiss Institute for Nuclear Research (SIN) is upgrading their proton accelerator to 1 to 2 mA Beam current at 600 MeV. Molten Pb-Bi is being considered as a beam stop. The materials in the beam stop must be chemically compatible with molten Pb-Bi, retain ductility and strength, and have a lifetime of at least six months. In a joint venture between the United States and SIN, four capsules were designed and loaded with eight tensile samples. The tensile samples were Ta, Cr (Fe-2 1/4% Cr-1% Mo… more
Date: January 1, 1985
Creator: Nicol, A. G.; Brown, R. D. & Cook, J. H.
Partner: UNT Libraries Government Documents Department
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Effects of sodium environment on the mechanical properties of Fe-2 1/4Cr-1Mo steel

Description: Mechanical property data on isothermally annealed, thermally aged, and sodium-exposed Fe-2 1/4Cr-1Mo steel are analyzed to evaluate the influence of the sodium environment as well as the effects of the microstructural and compositional changes that occur in the steel during long-term exposure to sodium. Correlations are developed to predict the environmental effects on tensile, creep, fatigue, and creep-fatigue properties of Fe-2 1/4Cr-1Mo steel in sodium. The results indicate that at temperatu… more
Date: September 1, 1983
Creator: Chopra, O,K.
Partner: UNT Libraries Government Documents Department
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H-division quarterly report, October--December 1977. [Lawrence Livermore Laboratory]

Description: The Theoretical EOS Group develops theoretical techniques for describing material properties under extreme conditions and constructs equation-of-state (EOS) tables for specific applications. Work this quarter concentrated on a Li equation of state, equation of state for equilibrium plasma, improved ion corrections to the Thomas--Fermi--Kirzhnitz theory, and theoretical estimates of high-pressure melting in metals. The Experimental Physics Group investigates properties of materials at extreme co… more
Date: February 10, 1978
Partner: UNT Libraries Government Documents Department
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Literature search for the non-aqueous separation of zinc from fuel rod cladding. [After dissolution in liquid metal]

Description: This report reviews the literature of processes for the nonaqueous separation of zinc from dissolved fuel assembly cladding. The processes considered were distillation, pyrochemical processing, and electrorefining. The last two techniques were only qualitatively surveyed while the first, distillation, was surveyed in detail. A survey of available literature from 1908 through 1978 on the distillation of zinc was performed. The literature search indicated that a zinc recovery rate in excess of 95… more
Date: June 21, 1980
Creator: Sandvig, R. L.; Dyer, S. J.; Lambert, G. A. & Baldwin, C. E.
Partner: UNT Libraries Government Documents Department
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Solar Central Receiver Hybrid Power Systems sodium-cooled receiver concept. Final report. Volume III. Appendices

Description: The overall, long term objective of the Solar Central Receiver Hybrid Power System is to identify, characterize, and ultimately demonstrate the viability and cost effectiveness of solar/fossil, steam Rankine cycle, hybrid power systems that: (1) consist of a combined solar central receiver energy source and a nonsolar energy source at a single, common site, (2) may operate in the base, intermediate, and peaking capacity modes, (3) produce the rated output independent of variations in solar inso… more
Date: January 1, 1980
Partner: UNT Libraries Government Documents Department
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Lithium corrosion/mass transfer test facility

Description: Liquid lithium is a leading candidate as a tritium breeding material for fusion reactors because of its good breeding and heat-transfer characteristics. This paper describes a new experimental facility for investigating the corrosion/mass transfer/deposition mechanisms at characteristic velocities and system temperatures. This test facility, which is constructed of ferritic/martensitic steel (Fe-9Cr-1Mo), simulates conditions projected for a liquid metal heat transport system. The test facility… more
Date: February 1, 1988
Creator: Smith, D. L.; Chopra, O. K. & Hull, A. B.
Partner: UNT Libraries Government Documents Department
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Soft-sphere model for liquid metals

Description: A semi-empirical soft-sphere model of fluids is modified for application to the thermodynamic properties of liquid metals. Enthalpy, volume, and sound speed are computed as functions of temperature for 13 metals and compared with experimental data. Critical points and coexistence curves are also computed and compared with experimental data, where these have been measured. Strengths and weaknesses of the model are discussed.
Date: November 8, 1977
Creator: Young, D.A.
Partner: UNT Libraries Government Documents Department
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Liquid metal heat transfer issues

Description: An alkali liquid metal cooled nuclear reactor coupled with an alkali metal Rankine cycle provides a practicable option for space systems/missions requiring power in the 1 to 100 MW(e) range. Thermal issues relative to the use of alkali liquid metals for this purpose are identified as these result from the nature of the alkali metal fluid itself, from uncertainties in the available heat transfer correlations, and from design and performance requirements for system components operating in the ear… more
Date: January 1, 1984
Creator: Hoffman, H.W. & Yoder, G.L.
Partner: UNT Libraries Government Documents Department
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Liquid-metal flow through a thin-walled elbow in a plane perpendicular to a uniform magnetic field

Description: This paper presents analytical solutions for the liquid-metal flow through two straight pipes connected by a smooth elbow with the same inside radius. The pipes and the elbow lie in a plane which is perpendicular to a uniform, applied magnetic field. The strength of the magnetic field is assumed to be sufficiently strong that inertial and viscous effects are negligible. This assumption is appropriate for the liquid-lithium flow in the blanket of a magnetic confinement fusion reactor, such as a … more
Date: April 1, 1986
Creator: Walker, J.S.
Partner: UNT Libraries Government Documents Department
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Final Report-Passive Safety Optimization in Liquid Sodium-Cooled Reactors.

Description: This report summarizes the results of a three-year collaboration between Argonne National Laboratory (ANL) and the Korea Atomic Energy Research Institute (KAERI) to identify and quantify the performance of innovative design features in metallic-fueled, sodium-cooled fast reactor designs. The objective of the work was to establish the reliability and safety margin enhancements provided by design innovations offering significant potential for construction, maintenance, and operating cost reductio… more
Date: August 13, 2007
Creator: Cahalana, J. E. & Hahn, D.
Partner: UNT Libraries Government Documents Department
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HEDL FACILITIES CATALOG 400 AREA

Description: The purpose of this project is to provide a sodium-cooled fast flux test reactor designed specifically for irradiation testing of fuels and materials and for long-term testing and evaluation of plant components and systems for the Liquid Metal Reactor (LMR) Program. The FFTF includes the reactor, heat removal equipment and structures, containment, core component handling and examination, instrumentation and control, and utilities and other essential services. The complex array of buildings and … more
Date: March 1, 1987
Creator: Mayancsik, B. A.
Partner: UNT Libraries Government Documents Department
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Overview of Idaho National Laboratory's Hot Fuels Examination Facility

Description: The Hot Fuels Examination Facility (HFEF) at the Materials and Fuels Complex (MFC) of the Idaho National Laboratory was constructed in the 1960’s and opened for operation in the 1975 in support of the liquid metal fast breeder reactor research. Specifically the facility was designed to handle spent fuel and irradiated experiments from the Experimental Breeder Reactor EBRII, the Fast Flux Test Facility (FFTF), and the Transient Reactor Test Facility (TREAT). HFEF is a large alpha-gamma facility … more
Date: September 1, 2007
Creator: Robinson, Adam B.; Lind, R. Paul & Wachs, Daniel M.
Partner: UNT Libraries Government Documents Department
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Verification Test Suite (VERTS) For Rail Gun Applications using ALE3D: 2-D Hydrodynamics & Thermal Cases

Description: A verification test suite has been assessed with primary focus on low reynolds number flow of liquid metals. This is representative of the interface between the armature and rail in gun applications. The computational multiphysics framework, ALE3D, is used. The main objective of the current study is to provide guidance and gain confidence in the results obtained with ALE3D. A verification test suite based on 2-D cases is proposed and includes the lid-driven cavity and the Couette flow are inves… more
Date: April 17, 2008
Creator: Najjar, F M; Solberg, J & White, D
Partner: UNT Libraries Government Documents Department
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Final Report: "Large-Eddy Simulation of Anisotropic MHD Turbulence"

Description: To acquire better understanding of turbulence in flows of liquid metals and other electrically conducting fluids in the presence of steady magnetic fields and to develop an accurate and physically adequate LES (large-eddy simulation) model for such flows. The scientific objectives formulated in the project proposal have been fully completed. Several new directions were initiated and advanced in the course of work. Particular achievements include a detailed study of transformation of turbulence … more
Date: June 23, 2008
Creator: Zikanov, Oleg
Partner: UNT Libraries Government Documents Department
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