Coupled Hydrodynamic-Structural Response Analysis of Piping Systems (open access)

Coupled Hydrodynamic-Structural Response Analysis of Piping Systems

This report describes in detail the expansion of the ICEPEL code for the coupled hydrodynamic-structural response analysis of pipe-elbow loops to general piping systems. A generalized piping-component model, a branching tce junction, and a surge-tank model are introduced and coupled with the pipe-elbow loop model so that a general piping system under the effect of internally traveling pressure pulses can be analyzed hydrodynamically, as well as structurally.
Date: 1978?
Creator: A-Moneim, M. T.
System: The UNT Digital Library
ICEPEL Analysis of and Comparison with Simple Elastic-Plastic Piping Experiments (open access)

ICEPEL Analysis of and Comparison with Simple Elastic-Plastic Piping Experiments

The results of simple elastic-plastic piping experiments for straight pipes and single-elbow loop systems are interpreted and evaluated. The experiments are also analyzed by the ICEPEL piping code, and the analytical results are compared against the experimental data.
Date: December 1978
Creator: A-Moneim, M. T.
System: The UNT Digital Library
Advanced Fuel Cell Development Progress Report: October-December 1977 (open access)

Advanced Fuel Cell Development Progress Report: October-December 1977

Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes work aimed at understanding and improving the performance of fuel cells having molten alkali-carbonate mixtures as electrolytes; the fuel cells operate at temperatures near 925 K.
Date: March 1978
Creator: Ackerman, J. P.; Kinoshita, K.; Finn, P. A.; Sim, J. W. & Nelson, P. A.
System: The UNT Digital Library
Advanced Fuel Cell Development Progress Report: April-June 1978 (open access)

Advanced Fuel Cell Development Progress Report: April-June 1978

Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes efforts directed toward understanding and improving the components of molten-carbonate-electrolyte fuel cells operated at temperatures near 925 K.
Date: August 1978
Creator: Ackerman, J. P.; Pierce, Robert Dean; Nelson, P. A.; Arons, R. M.; Kinoshita, K.; Sim, J. W. et al.
System: The UNT Digital Library
Addendum to a Proposal for ATLAS: a Precision-Ion Accelerator at Argonne National Laboratory, December 1978 (open access)

Addendum to a Proposal for ATLAS: a Precision-Ion Accelerator at Argonne National Laboratory, December 1978

This revised proposal for the construction of the Argonne Tandem-Linac Accelerator System (ATLAS) is in all essentials the same as the proposal originally presented to NUSAC in March 1978. The only differences worth mentioning are the plan to expand the experimental area somewhat more than was originally proposed and an increased cost, brought about principally by inflation. The outline presented is the same (with minor change in wording) as in the original document, reproduced here for the convenience of the reader.
Date: 1978
Creator: Argonne National Laboratory
System: The UNT Digital Library
Community Systems Program: Its Goals and Accomplishments, 1978 (open access)

Community Systems Program: Its Goals and Accomplishments, 1978

The Community Systems Program is concerned with conserving energy and scarce fuels through new methods of satisfying the energy needs of American communities. These programs are designed to develop innovative ways of combining current, emerging, and advanced technologies into Integrated Community Energy Systems (ICES) that could furnish any, or all, of the energy-using services of a community. The key goals of the Community System Program then, are to identify, evaluate, develop, demonstrate, and deploy energy systems and community designs that will optimally meet the needs of various communities. Integrated systems offer considerable potential for fuel substitution, thereby allowing the use of non-scarce fuel resources that would not be economically usable in smaller unintegrated systems. Input energy sources for such systems may include low-grade waste heat, solid and liquid wastes, solar and geothermal heat, seawater heat dissipation, and use of less-scarce fuels, such as coal and biomass. A Grid-Connected ICES uses a central co-generation plant and distribution system to provide heating, cooling, and electrical energy services. During 1977, contracts for the following Grid-Connected ICES (G-C ICES) demonstration teams were negotiated: City of Independence, Missouri; Clark University; City of Trenton, New Jersey; Health Education Authority of Louisiana (HEAL); and University of Minnesota. …
Date: April 1978
Creator: Argonne National Laboratory
System: The UNT Digital Library
Environmental Monitoring at Argonne National Laboratory, Annual Report: 1977 (open access)

Environmental Monitoring at Argonne National Laboratory, Annual Report: 1977

Annual report discussing results of environmental monitoring program to determine Argonne operations' effect on environment.
Date: March 1978
Creator: Argonne National Laboratory
System: The UNT Digital Library
Light-Water-Reactor Safety Research Program Quarterly Progress Report: January-March 1978 (open access)

Light-Water-Reactor Safety Research Program Quarterly Progress Report: January-March 1978

Quarterly report summarizing research and development by Argonne National Laboratory on water-reactor-safety heat-transfer and flow problems, including: Loss-of-coolant Accident Research: Heat Transfer and Fluid Dynamics, Transient Fuel Response and Fission-product Release Program, Mechanical Properties of Zircaloy Containing Oxygen,and Steam-explosion Studies.
Date: 1978?
Creator: Argonne National Laboratory
System: The UNT Digital Library
Light-Water-Reactor Safety Research Program Quarterly Progress Report: July-September 1977 (open access)

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

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
System: The UNT Digital Library
Light-Water-Reactor Safety Research Program, Quarterly Progress Report: October-December 1977 (open access)

Light-Water-Reactor Safety Research Program, Quarterly Progress Report: October-December 1977

Quarterly progress report summarizing work on water-reactor-safety problems: loss of coolant accident research, transient fuel response and fission-product release program, and mechanical properties of zircaloy containing oxygen.
Date: 1978?
Creator: Argonne National Laboratory
System: The UNT Digital Library
Proceedings of the 1978 Symposium on Instrumentation and Control for Fossil Demonstration Plants : June 19-21, 1978, Newport Beach Marriott, Newport Beach, California (open access)

Proceedings of the 1978 Symposium on Instrumentation and Control for Fossil Demonstration Plants : June 19-21, 1978, Newport Beach Marriott, Newport Beach, California

This conference covers various aspects of fossil-fuel power plants based on coal or coal-conversion products, as well as the process control equipment involved in the conversion or combustion processes.
Date: June 1978
Creator: Argonne National Laboratory
System: The UNT Digital Library
Physics of Reactor Safety, Quarterly Report: October-December 1977 (open access)

Physics of Reactor Safety, Quarterly Report: October-December 1977

Quarterly progress report summarizing work done in Argonne National Laboratory's Applied Physics Division and Components Technology Division. The work in the Applied Physics Division includes reports on reactor safety program by members of the Reactor Safety Appraisals Group, Monte Carlo analysis of safety-related critical assembly experiments by members of the Theoretical Fast Reactor Physics Group, and Planning of Safety-Related (ZPR) Planning and Experiments Group. Work on reactor core thermal-hydraulic code development performed in the Components Technology Division is also included in this report.
Date: March 1978
Creator: Argonne National Laboratory. Applied Physics Division.
System: The UNT Digital Library
Chemical Engineering Division Research Highlights (open access)

Chemical Engineering Division Research Highlights

Report on electrochemical energy development, including development of advanced, high-temperature lithium/metal sulfide batteries for vehicle propulsion and stationary energy storage.
Date: August 1978
Creator: Argonne National Laboratory. Chemical Engineering Division.
System: The UNT Digital Library
Chemical Engineering Division Research Highlights 1978 (open access)

Chemical Engineering Division Research Highlights 1978

Report of activities at Argonne Chemical Engineering Division, including lithium/metal sulfide batteries, electro-chemical project management, advanced fuel cell development, utilization of coal, magnetohydrodynamics, solar energy, fast reactor chemistry, and fuel cycles.
Date: 1978
Creator: Argonne National Laboratory. Chemical Engineering Division.
System: The UNT Digital Library
Studies of Nuclear Waste Migration in Geologic Media, Annual Report: November 1976-October 1977 (open access)

Studies of Nuclear Waste Migration in Geologic Media, Annual Report: November 1976-October 1977

Annual report of the Argonne National Laboratory Chemical Engineering Division regarding studies of nuclear waste migration in geologic media. This report discusses research regarding confinement of nuclear waste in geologic formations as a method of permanently disposing of the waste.
Date: March 1978
Creator: Argonne National Laboratory. Chemical Engineering Division.
System: The UNT Digital Library
Materials Technology for Coal-Conversion Processes Progress Report: July-December 1977 (open access)

Materials Technology for Coal-Conversion Processes Progress Report: July-December 1977

Progress report on the activities of the Argonne National Laboratory Materials Science Division regarding studies done on refractory concretes and metallic materials being used or intended for use in coal-conversion processes, erosive wear, nondestructive testing, corrosion, chemical degradation, and failure analysis.
Date: 1978?
Creator: Argonne National Laboratory. Materials Science Division.
System: The UNT Digital Library
Materials Technology for Coal-Conversion Processes Quarterly Report: January-March 1978 (open access)

Materials Technology for Coal-Conversion Processes Quarterly Report: January-March 1978

Quarterly report on the activities of the Argonne National Laboratory Materials Science Division regarding studies on ceramic (refractory) and metallic materials being used or intended for use in coal-conversion processes.
Date: 1978?
Creator: Argonne National Laboratory. Materials Science Division.
System: The UNT Digital Library
Physics Division Annual Review: 1 April 1977-31 March 1978 (open access)

Physics Division Annual Review: 1 April 1977-31 March 1978

Report on various studies in the physics division of Argonne National Laboratory.
Date: 1978?
Creator: Argonne National Laboratory. Physics Division.
System: The UNT Digital Library
Radiological and Environmental Research Division Annual Report: Part 3, Ecology, January-December 1978 (open access)

Radiological and Environmental Research Division Annual Report: Part 3, Ecology, January-December 1978

Annual report of the Argonne National Laboratory Radiological and Environmental Research Division regarding activities related to ecology. This report includes studies on the effects of sulfur dioxide on Midwestern grain crops and the addition of the new research vessel, the Ekos.
Date: 1978?
Creator: Argonne National Laboratory. Radiological and Environmental Research Division.
System: The UNT Digital Library
F1 Phenomenological Test on Fuel Motion : Final Report (open access)

F1 Phenomenological Test on Fuel Motion : Final Report

TREAT F-series tests are being conducted to provide data on fuel motion in an LMFBR during a hypothetical loss-of-flow accident. Fuel and fuel-boundary conditions in an LMFBR subassembly following sodium voiding and dryout under loss-of-flow conditions are simulated in each F-series test. Simulation is achieved with a single fuel element surrounded by an annular nuclear-heated wall in a dry (no sodium) test capsule. The area inside the heated wall was selected to represent the area inside the perimeter of an LMFBR coolant channel. Test F1 was conducted with an irradiated fuel element to investigate the effect of fission gas on fuel motion at design power levels following cladding melting and drainage. The principal conclusion from Test F1 is that fission products retarded, but did not prevent, eventual fuel collapse. The collapse was retarded by a fuel/fission-product froth that prevented fuel collapse until the fission products separated from the partially molten fuel. The fuel motion observed in F1 represents a particular type of fuel (burnup of 2.35 at.%, power rating of 394 W/cm) transient heated at design power rating.
Date: May 1978
Creator: Argonne National Laboratory. Reactor Analysis and Safety Division.
System: The UNT Digital Library
Domain and Surface Structures of Sodium Tungsten Bronzes, NaxWO₃ (0.4 [x [1) (open access)

Domain and Surface Structures of Sodium Tungsten Bronzes, NaxWO₃ (0.4 [x [1)

The domain and surface structures of metallic sodium tungsten bronzes, NaxWO₃, 0.4 < x < 1, were studied using optical microscopy, supplemented by chemical methods, photoelectron spectroscopy, electron microscopy, etc. The birefringent, multidomain structure of the bronze is exhibited by a sodium-deficient, epitaxial surface film and hence is not, as reported elsewhere, a bulk property. The film can be synthesized by anodic electrolysis in alkaline solution and can exist only epitaxially with the substrate. It is chemically inert, translucent, and often laminated to a multilayered film. The film domain is hypersensitive to lateral stress and to thermal change, and appears to be modulated by minute structural changes of the substrate. This epitaxial modulation of the film is strikingly large at the phase transitions of the substrate induced by slightly different tiltings of the oxygen octahedra. The domain-wall movement is often slow enough to be visible, and that by thermal effect is occasionally accompanied by an audible, high-pitched, snapping sound.
Date: September 1978
Creator: Atoji, Masao
System: The UNT Digital Library
Proceedings of the Third Post-Accident Heat Removal Information Exchange November 2-4, 1977, Argonne National Laboratory, Argonne, Illinois (open access)

Proceedings of the Third Post-Accident Heat Removal Information Exchange November 2-4, 1977, Argonne National Laboratory, Argonne, Illinois

Papers presented at the third Post-Accident Heat Removal Information Exchange concerning heat distribution and criticality considerations, particulate-bed phenomena, pool heat transfer and melt-front phenomena, behavior of heated concrete and sodium-concrete interactions, design-related studies, gas bubbling and boiling effects, and materials interactions at high temperatures and experimental methods.
Date: 1978?
Creator: Baker, Louis, Jr. & Bingle, James D.
System: The UNT Digital Library
Reactor Physics Studies in the Steam Flooded GCFR-Phase 2 Critical Assembly (open access)

Reactor Physics Studies in the Steam Flooded GCFR-Phase 2 Critical Assembly

A possible accident scenario in a Gas-Cooled Fast Reactor (GCFR) is the leakage of secondary steam into the core. Considerable analytical effort has gone into the study of the effects of such an accidental steam entry. The work described in this report represents the first full scale experimental study of the steam-entry phenomenon in GCFRs. The reference GCFR model used for the study was the benchmark GCFR Phase II assembly, and polyethylene foam was used to provide a very homogeneous steam simulation.
Date: August 1978
Creator: Bhattacharyya, S. K.
System: The UNT Digital Library
Viscosity of Molten Alumina (open access)

Viscosity of Molten Alumina

In the analysis of LMFBR core-containment and heat-removal problems associated with hypothetical core-disruptive accidents, viscosity data on molten ceramics are needed to help analyze the convective heat transfer and flow patterns within liquid pools. An oscillating cup viscometer has been used to measure the viscosity of molten alumina in the temperature range from 2400 to 2750/sup 0/K. The data are represented by the equation: log eta = 11448/T - 8.2734 where the viscosity, eta, is given in Pascal seconds and the temperature, T, is in Kelvins.
Date: 1978?
Creator: Blomquist, R. A.; Fink, J. K. & Leibowitz, L.
System: The UNT Digital Library