Technical Report Archive and Image Library (TRAIL) - Browse


Tracheobronchial Geometry: Human, Dog, Rat, Hamster - A Compilation of Selected Data from the Project Respiratory Tract Deposition Models

Description: From abstract: "This report documents data collected by detailed measurements of the geometrical features of the tracheobronchial conducting airways of the lungs of four mammalian species."
Date: March 1976
Creator: Raabe, Otto G.; Yeah, Hsu-Chi; Schum, Michael G. & Phalen, Robert F.
Partner: UNT Libraries Government Documents Department

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

Description: 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
Partner: UNT Libraries Government Documents Department

An Analytical Study of the Feasibility of Irradiating U233/Th232 Metal Fuel Experiments in EBR-II

Description: Recent concerns about the proliferation and diversion of plutonium have lead to reconsideration of Uranium-233/Thorium-232 fuel cycles. Although thorium fuels have been studied earlier, much of that work is incomplete; consequently, additional irradiation studies will be necessary.
Date: 1979?
Creator: Foltman, A. J. & Meneghetti, D.
Partner: UNT Libraries Government Documents Department

Monte Carlo-Based Validation of the ENDF/MC²-II/SDX Cell Homogenization Path

Description: The results are presented of a program of validation of the unit cell homogenization prescriptions and codes used for the analysis of Zero Power Reactor (ZPR) fast breeder reactor critical experiments. The ZPR drawer loading patterns comprise both plate type and pin-calandria type unit cells. A prescription is used to convert the three dimensional physical geometry of the drawer loadings into one dimensional calculational models. The ETOE-II/MC²-II/SDX code sequence is used to transform ENDF/B basic nuclear data into unit cell average broad group cross sections based on the 1D models. Cell average, broad group anisotropic diffusion coefficients are generated using the methods of Benoist or of Gelbard. The resulting broad (approx. 10 to 30) group parameters are used in multigroup diffusion and S(su n) transport calculations of full core XY or RZ models which employ smeared atom densities to represent the contents of the unit cells.
Date: April 1979
Creator: Wade, D. C.
Partner: UNT Libraries Government Documents Department

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

Description: 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.
Partner: UNT Libraries Government Documents Department

Materials Technology for Coal-Conversion Processes Quarterly Report: July-September 1978

Description: Quarterly report on the activities of the Argonne National Laboratory Materials Science Division regarding studies on ceramic (refractory) and metallic materials presently being used or intended for use in coal conversion processes. The program entails studies of erosive wear, nondestructive testing, corrosion, refractory degradation, and failure analysis.
Date: 1978
Creator: Ellingson, W. A.
Partner: UNT Libraries Government Documents Department

Radiological and Environmental Research Division Annual Report: Part 1, Fundamental Molecular Physics, October 1977-September 1978

Description: Annual report of the Argonne National Laboratory Radiological and Environmental Research Division regarding activities related to molecular physics and chemistry. This report discusses a study on the physical properties and the chemical reactions of atmospheric constituents, with emphasis on the role of pollutants arising from the use of fossil fuels. Special effort is being placed on understanding nucleation phenomena through the study of the molecular properties of gas phase clusters.
Date: October 1977
Creator: Rowland, R. E.
Partner: UNT Libraries Government Documents Department

Development of a MK-II Loop to Simulate Reactor Hydraulic Conditions

Description: The Mk-IIC Integral Loop was modified to provide an in-pile experimental apparatus that would simulate the subassembly coolant flow rate and inlet pressure head of the Fast Test Reactor (FTR). There were two main design changes. First, the safety dump tanks were removed from the Mk-IIC loop and replaced by a second annular linear induction pump (ALIP). Second, a flow restricting orifice was sized so that the hydraulic requirements of prototypical test-section coolant velocity and pressure head would be achieved. The resulting redesigned loop was used for the in-pile TREAT transient over-power Test H6, which investigated fuel sweep-out and coolability following fuel-pin failure under hydraulic conditions typical of the FTR. The procedure reported here will help in the design of advanced TREAT vehicles such as the Mk-III loop.
Date: January 1979
Creator: Page, R. J. & Robinson, L. E.
Partner: UNT Libraries Government Documents Department

Experimental Validation of PTA-1 Computer Code for Pressure Transient Analysis Including the Effect of Pipe Plasticity

Description: The PTA-1 code for computing pressure transients in piping networks includes a computational model to treat the significant effect of plastic deformation of the piping on pulse propagation. Stanford Research Institute has completed an experimental program on the response of piping systems to internal pressure pulses which plastically deform portions of the piping. This report makes extensive comparisons between PTA-1 computations and these experimental results. The excellent agreement obtained for both pressure histories and strain histories for all the experiments indicates that the PTA-1 computational model for pipe plasticity effects is accurate. The computation-experiment comparisons also permit a number of observations and conclusions to be made on other aspects of computational modeling of pressure transients, particularly with respect to pulse propagation around elbows.
Date: July 1978
Creator: Youngdahl, C. K.; Kot, C. A. & Valentin, R. A.
Partner: UNT Libraries Government Documents Department

Symposium on Applications of Superconducting Quantum Interference Devices (SQUIDS) at University of Virginia, Charlottesville, Virginia, March 23, 1978

Description: The abstracts are given of thirteen papers presented at a ''SQUID Symposium'' organized by the Division of Materials Sciences of the U.S. Department of Energy and held March 23-25, 1978, at the University of Virginia. Since SQUID systems have already been utilized in feasibility demonstration in geothermal reservoir exploration, it was recognized that these devices also hold great potential for many other important scientific measurements. Many of these are energy-related, and others include forefront investigations in a diverse group of scientific areas, from biomedical to earthquake monitoring. Research in SQUIDs has advanced so rapidly in recent years that it was felt that a symposium to review the current status and future prospects of the devices would be timely. The abstracts given present an overview of work in this area and hopefully provide an opportunity to increase awareness among basic and applied scientists of the inherent implications of the extreme measurement sensitivity in advanced SQUID systems.
Date: 1978?
Creator: Falco, Charles M. & Clarke, John
Partner: UNT Libraries Government Documents Department

Loss-of-Flow Test L5 on FFTF-Type Irradiated Fuel

Description: Test L5 simulated a hypothetical loss-of-flow accident in an LMFBR using three (plutonium, uranium) dioxide fuel elements of the FTR type. The test elements were irradiated before TREAT Test L5 in the General Electric Test Reactor to 8 at. % burnup at about 40 kW/m. The pre-irradiation in GETR caused a fuel-restructuring range characteristic of moderate-power structure relative to the FTR. The test transient was devised so that a power burst would be initiated at incipient cladding melting after the loss of flow. The test simulation corresponds to a scenario for FTR in which fuel in high-power-structure subassemblies slump, resulting in a power excursion. The remaining subassemblies are subjected to this power burst. Test L5 addressed the fuel-motion behavior of the subassemblies in this latter category. Data from test-vehicle sensors, hodoscope, and post-mortem examinations were used to construct the sequence of events within the test zone. From these observations, the fuel underwent a predominantly dispersive event just after reaching a peak power six times nominal at, or after, scram. The fuel motion was apparently driven by the release of entrained fission-product gases, since fuel vapor pressure was deliberately kept below significant levels for the transient. The test remains show a wide range of microstructural evolution, depending on the extent of heat deposition along the active fuel column. Extensive fuel swelling was also observed as a result of the lack of the cladding restraint. The results of the thermal-hydraulic calculations with the SAS3A code agreed qualitatively with the postmortem results with respect to the extent of the melting and the dispersal of cladding and fuel. However, the calculated times of certain events did not agree with the observed times.
Date: March 1978
Creator: Simms, R.; Gehl, S. M.; Lo, R. K. & Rothman, Alan B.
Partner: UNT Libraries Government Documents Department

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

Description: 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
Partner: UNT Libraries Government Documents Department

HYCSOS : A Chemical Heat Pump and Energy Conversion System Based on Metal Hydrides

Description: The current status of the HYCSOS chemical heat pump and energy conversion system based on metal hydrides is described. Heat transfer fluid loops were insulated and modified for isothermal operation. Software development for HYCSOS manual mode operation was completed. Routines to handle data acquisition, logging, compression, correction and plotting, using a Tektronix Graphics system with flexible disk data storage, provide a rapid and versatile means of presenting HYCSOS data for analysis. Advanced concept heat exchangers to improve the heat transfer of the hydride bed with the heat transfer fluid are discussed. Preliminary tests made with a LaNi5 loaded aluminum foam test unit showed that heat transfer properties are very markedly improved. Thermodynamic expressions are applied to the selection of alloys for use in HYCSOS. The substitution of aluminum for nickel in AB5 type alloys is shown to reduce hysteresis and permits the use of potentially lower cost materials with added flexibility for the optimization of engineering design and performance characteristics of the hydride heat pump system. Transient thermal measurements on hydride beds of CaNi5 and LaNi5 show no deterioration with cycling. Relatively slow heat transfer between the hydride beds and heat transfer fluid in the coiled tube heat exchangers is indicated by temperature lag of the bed and heat transfer fluid. Improved heat transfer is anticipated with aluminum foam heat exchangers.
Date: April 1979
Creator: Sheft, Irving; Gruen, Dieter M. & Lamich, George
Partner: UNT Libraries Government Documents Department

Evaluation of Ceramic Refractories for Slagging Gasifiers : Summary of Progress to Date

Description: Commercial refractories were tested for up to 500 h in both basic and acidic slags. The slag compositions typify those expected in slagging coal gasifiers. The slag temperatures ranged up to 1600 degrees C. Compositions tested have included silicon carbides, chrome-alumina-magnesia spinels, and alumina and magnesia-based refractories with various amounts of chromia and silica. In some tests, the cold faces were water cooled. With water cooling, the silicon carbides showed virtually no attack after 500 h. In the absence of water cooling, the chrome-alumina-magnesia spinels were the most resistant to slag attack but were subject to thermal-shock cracking. Alumina-chrome refractories performed well in acid slags when water cooled, are probably more stable than silicon carbide in coal-gasification atmospheres, and, in the form of ramming mixes, showed excellent thermal-shock resistances. Plans for future testing are described.
Date: September 1978
Creator: Kennedy, C. R.; Swaroop, R.; Jones, D. J.; Fousek, R. J.; Poeppel, R. B. & Stahl, D.
Partner: UNT Libraries Government Documents Department

Design and Installation Manual for Thermal Energy Storage

Description: The purpose for this manual is to provide information on the design and installation of thermal energy storage in solar heating systems. It is intended for contractors, installers, solar system designers, engineers, architects, and manufacturers who intend to enter the solar energy business. The reader should have general knowledge of how solar heating systems operate and knowledge of construction methods and building codes. Knowledge of solar analysis methods such as f-chart, SOLCOST, DOE-1, or TRNSYS would be helpful. The information contained in the manual includes sizing storage, choosing a location for the storage device, and insulation requirements. Both air-based and liquid-based systems are covered with topics on designing rock beds, tank types, pump and fan selection, installation, costs, and operation and maintenance. Topics relevant to heating domestic water include safety, single- and dual-tank systems, domestic water heating with air- and liquid-based space heating system, and stand-alone domestic hot water systems. Several appendices present common problems with storage systems and their solutions, heat transfer fluid properties, heat exchanger sizing, and sample specifications for heat exchangers, wooden rock bins, steel tanks, concrete tanks, and fiberglass-reinforced plastic tanks.
Date: February 1979
Creator: Cole, Roger Lynn; Nield, Kenneth J.; Rohde, Raymond R. & Wolosewicz, R. M.
Partner: UNT Libraries Government Documents Department

The Status and Development Potential of Plate-Type Fuels for Research and Test Reactors

Description: A program of transient in-reactor experiments is being conducted by Argonne National Laboratory in the Transient Reactor Test (TREAT) facility to guide and support analyses of hypothetical core-disruptive accidents (HCDA) in liquid-metal fast breeder reactors (LMFBR). Test results provide data needed to establish the response of LMFBR cores to hypothetical accidents producing fuel failure, coolant boiling, and the movement of coolant, molten fuel, and molten cladding. These data include margins to fuel failure, the modes of failure and movements, and evidence for identification of the mechanisms which determine the failure and movements. A key element in the program is the fast-neutron hodoscope, which detects fuel movement as a function of time during experiments.
Date: March 1979
Creator: Stahl, D.
Partner: UNT Libraries Government Documents Department

Thermal Conductivity of the Helium-Argon System

Description: A semi-empirical relation for the thermal conductivity of helium-argon gas mixtures is suggested. The analyses used in support of the proposed conductivity relations are based on low-temperature (T < 800 degrees C) thermal conductivity data for helium, argon and helium-argon mixtures. The report is a compilation of available data and theories, and does not contain any new experimental results. With the approach presented here, one should be able to predict thermal conductivities of helium-argon mixtures to within 5% of their true values for temperatures up to 1200 K. The recommended equations are best estimates and should be treated as such. A definite need exists for experimental data to verify or modify the recommendation.
Date: February 1979
Creator: Purohit, A. & Moszynski, Jerzy R.
Partner: UNT Libraries Government Documents Department