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Advanced Fuel Cell Development Progress Report: October-December 1983

Description: Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes activities directed toward seeking alternative cathode materials to NiO for molten carbonate fuel cells.
Date: August 1984
Creator: Ackerman, J. P.; Pierce, Robert Dean; Nelson, P. A. & Arons, R. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Advanced Materials in the Manufacturing Revolution: Proceedings of the Conference Held at Argonne National Laboratory June 14, 1988

Description: A conference at Argonne National Laboratory for senior executives of small and medium-size manufacturing companies covered technical and managerial issues involved in adapting advanced materials and new manufacturing methods. Seven speakers discussed how high performance metals, alloys, ceramics, polymerics and their composites are replacing conventional mill-product materials and how these new materials are impacting manufacturing methods and products.
Date: February 1989
Creator: Nevitt, Michael V. & Peterson, Norman D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Advanced Thermoplastic Materials for District Heating Piping Systems

Description: The work described in this report represents research conducted in the first year of a three-year program to assess, characterize, and design thermoplastic piping for use in elevated-temperature district heating (DH) systems. The present report describes the results of a program to assess the potential usefulness of advanced thermoplastics as piping materials for use in DH systems.
Date: April 1988
Creator: Raske, D. T. & Karvelas, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Air Pollution and the Siting of Fossil Fuel Power Plants

Description: The decision to locate a fossil-fueled electrical power plant on a particular site involves trade-offs among the costs of: (1) land acquisition, (2) plant construction, operation, and maintenance, (3) power transmission, and (4) air pollution damage to humans, animals, plants and materials. The fourth of these, pollution costs, has been of great concern in recent years. But seldom, if ever, are the specific dollar trade-offs between the environmental and the other costs associated with site sel… more
Date: 1976
Creator: Fishelson, Gideon; Rausser, Gordon C. & Cohen, Alan S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Algebraic Theory of Program Specification and Correctness Using Symmetry Operations

Description: This report applies some methods from the theory of group representation to the questions of program specification and knowledge about programs. The theory is that of a program as a transformation on a state space, and operators commuting with that transformation being symmetries of the program, means of specifying properties, and generators of program invariants. Because a program can simulate a system in the real world, there is a corresponding model of engineered artifacts, that is, manmade … more
Date: March 1987
Creator: Gabriel, John R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ALPR Preliminary Design Study (Argonne Low Power Reactor) Phase 1

Description: A preliminary design study, Phase I of the ALPR project, has been made in accordance with the Army Reactors Branch specifications for a nuclear "package" power plant with a 200-260-kw electric and 400 kw heating capacity. The plant is to be installed at the Idaho Reactor Testing Station as a prototype for remote arctic installations. The "conventional" power plant as well as the exterior reactor components are described in the accompanying report and cost estimate by Pioneer Service and Enginee… more
Date: April 20, 1956
Creator: Treshow, M.; Pearlman, H.; Rossin, D. & Shaftman, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Alternative Fuel Cycle Options : Performance Characteristics and Impact on Nuclear Power Growth Potential

Description: The fuel utilization characteristics for LWR, SSCR, CANDU and LMFBR reactor concepts are quantified for various fuel cycle options, including once-through cycles, thorium cycles, and denatured cycles. The implications of various alternative reactor deployment strategies on the long-term nuclear power growth potential are then quantified in terms of the maximum nuclear capacity that can be achieved and the growth pattern over time, subject to the constraint of a fixed uranium-resource base. The … more
Date: September 1977
Creator: Chang, Y. I.; Till, C. E.; Rudolph, R. R.; Deen, J. R. & King, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Alternative Library Under 4. 2 BSD UNIX on a VAX 11/780

Description: This paper describes an alternative library of elementary functions prepared for use with the standard Fortran compiler under 4.2 BSD UNIX on a VAX 11/780. The library, written in C and based on the book ''Software Manual for the Elementary Functions'' by Cody and Waite, offers improved accuracy over the standard system library, as well as additional capabilities. Listings and output from the ELEFUNT suite of test programs are included in the appendix.
Date: February 1986
Creator: Cody, William James
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Alternatives for Conversion to Solid Interim Waste Forms of the Radioactive Liquid High-Level Wastes Stored at the Western New York Nuclear Service Center

Description: Techniques for isolating and solidifying the nuclear wastes in the storage tanks at the Western New York Nuclear Service Center plant have been examined. One technique involves evaporating the water and forming a molten salt containing the precipitated sludge. The salt is allowed to solidify and is stored in canisters until processing into a final waste form is to be done. Other techniques involve calcining the waste material, then agglomerating the calcine with sodium silicate to reduce its di… more
Date: August 1981
Creator: Vogler, S.; Trevorrow, L. E.; Ziegler, A. A. & Steindler, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Alternatives for Disposal of Raffinate from the TRUEX Process

Description: Possible methods for disposing of the immobilized raffinate from TRUEX processing are reviewed. The purpose of the TRUEX process is to extract transuranium elements from high-level and TRU wastes into a small volume that can be managed at lower cost than that of the original wastes. The raffinate from the TRUEX process, containing negligible concentrations of transuranium elements, would be combined with salt solutions also derived from processing high-level waste, and the mixture would be conv… more
Date: December 1989
Creator: Trevorrow, L. E. & Vandegrift, G. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of a Cylindrical Shell Vibrating in a Cylindrical Fluid Region

Description: Analytical and experimental methods are presented for evaluating the vibration characteristics of cylindrical shells such as the thermal liner of the Fast Flux Test Facility (FFTF) reactor vessel. The NASTRAN computer program is used to calculate the natural frequencies, mode shapes, and response to a harmonic loading of a thin, circular cylindrical shell situated inside a fluid-filled rigid circular cylinder. Solutions in a vacuum are verified with an exact solution method and the SAP IV compu… more
Date: August 1976
Creator: Chung, Ho; Mulcahy, T. M.; Turula, P. & Jendrzejczyk, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of an Internally Pressurized Prismatic Cell Can

Description: This report contains an elastic stress and displacement analysis of a prismatic cell can subjected to internal pressure. A computer program was written to perform the analysis. The results show that, for the geometry chosen, the thicknesses of the cell-can walls and the magnitude of the internal pressure are the most important parameters that determine the stresses and deformations of the cell can. Recommendations for future studies are included.
Date: April 1980
Creator: Majumdar, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of Cracked Core Spray Injection Line Piping from the Quad Cities Units 1 and 2 Boiling Water Reactors

Description: Elbow assemblies and adjacent piping from the loops A and B core spray injection lines of Quad Cities Units 1 and 2 Boiling Water Reactors have been examined in order to determine the nature and causes of coolant leakages and flaw indications detected during hydrostatic tests and subsequent ultrasonic inspections. The elbow assemblies were found to contain multiple intergranular cracks in the weld heat-affected zones. The cracking was predominantly axial in orientation in the forged elbow and w… more
Date: December 1983
Creator: Diercks, D. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of EBR-II Low-Power Dosimetry Run 78C

Description: This report compares calculated reaction rates based on neutron-transport calculations in RZ and XY geometries with measured values from a low-power dosimetry test in EBR-II. Axial distributions of Uranium-235 and uranium-238 fission rates and uranium-238 capture rate are given for various radial locations along the length of the core and the axial reflectors, and along the length of the radial steel reflectors. Reaction rates, primarily at the reactor midplane, are given for a number of fissi… more
Date: December 1977
Creator: Franklin, F. C.; Ebersole, E. R. & Heinrich, R. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Analysis of Factors Influencing the Reliability of Retrievable Storage Canisters for Containment of Solid High-Level Radioactive Waste

Description: The reliability of stainless steel type 304L canisters for the containment of solidified high-level radioactive wastes in the glass and calcine forms was studied. A reference system, drawn largely from information furnished by Battelle Northwest Laboratories and Atlantic Richfield Hanford Company is described. Operations include filling the canister with the appropriate waste form, interim storage at a reprocessing plant, shipment in water to a Retrievable Surface Storage Facility (RSSF), inter… more
Date: August 1976
Creator: Mecham, W. J.; Seefeldt, Waldemar B. & Steindler, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of Heat-Pipe Absorbers in Evacuated-Tube Solar Collectors

Description: Heat transfer in evacuated-tube solar collectors with heat-pipe absorbers is compared with that for similar collectors with flow-through absorbers. In systems that produce hot water or other heated fluids, the heat-pipe absorber suffers a heat transfer penalty compared with the flow-through absorber, but in many cases the penalty can be minimized by proper design at the heat-pipe condenser and system manifold. The heat transfer penalty decreases with decreasing collector heat loss coefficient, … more
Date: February 1986
Creator: Hull, John R.; Schertz, William W. & Allen, John W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of Nonlinear Fluid Structure Interaction Transient in Fast Reactors

Description: A generalized Eulerian method is described for analyzing the fluid transients and the structural response in nuclear reactors under the postulated accident conditions. The phenomena considered are the wave propagation, slug impact, sodium spillage, bubble migration, and the fluid-structure interaction. The basic equations and numerical formulation are presented in detail. Sample calculations are given to illustrate the analysis. It is shown from the results that the implicit, iterative method u… more
Date: 1978
Creator: Yang, C. Y.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of Proposed Gamma-Ray Detection System for the Monitoring of Core Water Inventory in a Pressurized Water Reactor

Description: An initial study has been performed of the feasibility of employing an axial array of gamma detectors located outside the pressure vessel to monitor the coolant in a PWR. A one-dimensional transport analysis model is developed for the LOFT research reactor and for a mock-PWR geometry. The gamma detector response to coolant voiding in the core and down-comer has been determined for both geometries. The effects of various conditions (for example, time after shutdown, materials in the transport pa… more
Date: December 1987
Creator: Markoff, Diane Melanie
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Analysis of the High-Temperature Particulate Collection Problem

Description: Particulate agglomeration and separation at high temperatures and pressures are examined, with particular emphasis on the unique features of the direct-cycle application of fluidized-bed combustion. The basic long-range mechanisms of aerosol separation are examined, and the effects of high temperature and high pressure on usable collection techniques are assessed. Primary emphasis is placed on those avenues that are not currently attracting widespread research. The high-temperature, particulate… more
Date: October 1977
Creator: Razgaitis, Richard
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of the October 5, 1979 Lithium Spill and Fire in the Lithium Processing Test Loop

Description: On October 5, 1979, the Lithium Processing Test Loop (LPTL) developed a lithium leak in the electromagnetic (EM) pump channel, which damaged the pump, its surrounding support structure, and the underlying floor pan. A thorough analysis of the causes and consequences of the pump failure was conducted by personnel from CEN and several other ANL divisions. Metallurgical analyses of the elliptical pump channel and adjacent piping revealed that there was a significant buildup of iron-rich crystallit… more
Date: December 1981
Creator: Maroni, V. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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