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Advanced Fuel Cell Development Progress Report: July-September 1983
Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes activities seeking alternative cathode materials to NiO for molten carbonate fuel cells.
Advanced Fuel Cell Development Progress Report: July-September 1984
Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes studies directed toward seeking alternative cathode materials to NiO for molten carbonate fuel cells.
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.
Advanced Fuel Cell Development Progress Report: October-December 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.
Advanced Fuel Cell Development Progress Report: October-December 1979
Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes efforts directed toward understanding and improving components of molten carbonate fuel cells and have included operation of 10-cm square cells.
Advanced Fuel Cell Development Progress Report: October-December 1980
Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes efforts directed toward (1) developing alternative concepts for components of molten carbonate fuel cells and (2) improving understanding of component behavior.
Advanced Fuel Cell Development Progress Report: October-December 1981
Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes efforts directed toward (1) improving understanding of component behavior in molten carbonate fuel cells and (2) developing alternative materials and concepts for components. The principal focus was changed during this period from the development of cathodes fabricated from NiO and electrolyte supports of sintered y-LiA102 to an investigation of NiO cathode dissolution and deposition and a search for alternative cathode materials.
Advanced Fuel Cell Development Progress Report: October-December 1983
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.
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 1. Cost Analysis and Future Development
First part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. I-ii).
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 2. Plant Conceptual Studies
Second part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. II-i).
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients
Third part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 4. Steam Driven Coolant Pumps
Fourth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept
Fifth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Advanced Materials in the Manufacturing Revolution: Proceedings of the Conference Held at Argonne National Laboratory June 14, 1988
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.
Advanced Pressurized Water Reactor Study [Part 1]: Phase 1 Report
From preface: This report covers Phase I of the authorized work, consisting of determination of the specific reactor concept and size for the most economic reactor, preparation of a reference design of the most promising concept and estimated capital and generating costs, evaluation of the variations in cost as a function of unit size, and evaluation of the reductions in ultimate costs for a power station having multiple units of the same type.
Advanced Pressurized Water Reactor Study [Part 1, Supplement]: Phase 2--A Report
From introduction: This report details the progress of the Advanced Pressurized Water Reactor Study.
Advanced Pressurized Water Reactor Study [Part 3]: 235 Mw Coal-fired Generating Plant
"This study is one of four initiated in 1958 by the Division of Reactor Development, U.S. Atomic Energy Commission, to assess the feasibility of power generation through the use of certain types of nuclear reactors. These studies are available from the Office of Technical Services, U.S. Department of Commerce, Washington 25, D.C."
Advanced Seminar in Reactor Physics
The following report provides equations that result from a seminar in reactor physics.
An Advanced Sodium-Graphite Reactor Nuclear Power Plant
Abstract: This report describes an advanced sodium-cooled, graphite-moderated nuclear power plant which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency.
Advanced Test Reactor Burnout Heat Transfer Tests
From abstract: "Results of burnout test to determine the limiting heat flux in a simulated Advanced Test Reactor fuel element channel."
Advanced Test Reactor: Final Shielding Design Report
From abstract: "This report has been prepared as a design reference document describing the calculation methods and engineering results for shielding analysis work done during the design of the Advanced Test Reactor."
Advanced Test Reactor Servo Regulator Rod Test Program
From abstract: "Verify rod mechanism characteristics reported by the United Shoe Machinery Corporation, demonstrate that rod mechanism characteristics were compatible with reactor kinetics and that over-all reactor system behavior was stable, and to recommend system modifications needed for satisfactory performance."
Advanced Test Reactor Turbo Report
From abstract: "The time-dependent behavior of the Advanced Test Reactor was calculated by the Babcock & Wilcox Company on the Philco 2000 computer, using the Turbo depletion program."
Advanced Thermoplastic Materials for District Heating Piping Systems
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.
Advances in Coal Spectrometry: Absorption Spectrometry
Report from the U.S. Bureau of mines discussing the use of infared and ultraviolet-visible spectrometry to study the structure of coal and coal extracts.
Advances in Research on Mineral Resources, 1994
This report talks about some of the current domestic and international research activities of the Office of Mineral Resources, Geological Division of the USGS.
Advances Related to United States and International Mineral Resources: Developing Frameworks and Exploration Technologies
The following report provides information for the public good about the origin, quality, and quantity of mineral resources world-wide. This Bulletin reports progress on some of the current activities of the Office of Mineral Resources and reflects the necessity for an international perspective regarding mineral resources and research technology.
Advantages of Oxide Films as Bases for Aluminum Pigmented Surface Coatings for Aluminum Alloys
Report discussing both laboratory and weather-exposure corrosion tests showed conclusively that the protection afforded by aluminum pigmented spar varnish coatings applied to previously anodized aluminum surfaces was greatly superior to that afforded by the same coatings applied to surfaces which had simply been cleaned free from grease and not anodized.
The Advantages of Uniform Fuel Distribution for Air-Cooled Engines From Considerations of Cooling Requirements and Fuel Economy
"The purpose of this report is to show by analysis of existing data, pending direct experimental determination, the extent to which nonuniform distribution of fuel to cylinders of a multicylinder engine can produce temperature deviation and the benefits to be anticipated from attainment of uniform fuel distribution" (p. 1).
AEC Fuel Cycle Program Design and Fabrication of Special Assembly 9-L : Irradiation Performance Test of UO2-Cermet Fuel
Technical report describing a UO2-Mo cermet fuel assembly fabricated for long-term irradiation performance testing in the Vallecitos Boiling water Reactor. The design and fabrication histories of this assembly are described and pre-irradiation data on each individual rod are presented. Molybdenum was added to improve the bulk thermal conductivity of the fuel, so that fuel temperatures would remain comparatively low during high-power level operation of the fuel element. The molybdenum was incorporated into the compacts either as fibers or as a thin coating on individual UO2 particles. Fuel pellets were produced from these materials by vacuum hot pressing. The distribution of the molybdenum in both types of cermet fuels appeared favorable to good heat transfer. The fibers were oriented predominantly in the radial planes of the pellet as a result of the uni-directional compaction during the hot-pressing operation. In the pellets made from the coated particles, a continuous network of molybdenum occurred as a result of the coating welding together during the hot-pressing operation. The test assembly contains eight fuel rods; three contain UO2-Mo cermet, three contain the cermet produced from the coated particles, and two are for reference and contain the conventional sintered UO2 pellet fuel. The nominal outside diameter of the fuel rods is 1.308 cm (0.515 inch), and the clad wall thickness if 0.051 cm (0.020 inch). the cladding material is Type-304 stainless steel. The fuel pellets were all centerless ground to achieve a uniform outside diameter and thereby control the pellet-to-clad diametral clearance within a range of 0.076 to 0.102 mm (0.003 to 0.004 inch). Operation of the fuel rods will be at high specific power levels with surface heat fluxes of about 157 W/cm(2) (~500,000 Btu/h-ft(2)). The assembly was designed for a lifetime of 4.1 x 10(20) fission/cc (15,000 MWD/T) exposure.
AEC Group Shelter
Report regarding the study of an underground group-shelter meant to protect against nuclear blasts, radiation, and fallout. The report presents a design for such a shelter, the minimum requirements that such a shelter should meet, a description of its facilities, illustrations, and an operating manual.
AEC Hot Cells and Related Facilities
Foreward: The primary purpose of this report is to present as an accumulation of basic information on the hot cells constructed to date by the United States Atomic Energy Commission.
Fuel Cycle Program Progress Report: Thirteenth Quarter, July-September 1963
Quarterly progress report discussing activities related to the Vallecitos Boiling Water Reactor (VBWR) and related facilities
AEC Research and Development Report: Yield of Kr-85 and Xe-133 in the Thermal Neutron Fission of U-235 and Yield of Kr-85 in the Thermal Neutron Fission of Pu-239
We have made absolute radiochemical measurements of the yields of Kr-85 and Xe-133 in the thermal neutron fission of U-235, and of Kr-85 in the thermal neutron fission of Pu-239. For Kr-85 in U-235 fission, the mean of eight measurements gives the ratio, X/T, of fission yield to half-life: X/T = 0.0253%/yr; σ = 1.59%; 99-1 error of the mean = 2.41%. For Kr-85 in Pu-239 fission, the mean of three measurements gives X/T = 0.0092%/yr; σ = 4.3%. Here σ is the standard deviation of a single measurement expressed as percent of the mean. If the Kr-85 half-life is 10.8 (±4%) yr, the yields are U-235 fission: X = 0.273% (±5% of X). Pu- 239 fission: X = .0994%. The error estimate in the U-235 yield is an accuracy estimate compounded of estimated accuracies of 3% in the X/T value and 4% in the half life. For Xe-133 in U-235 fission, the mean of five measurements gives the yield: X = 6.62%; σ = 0.095% of X; accuracy = ±3% of X. The accuracy estimates are based on a detailed investigation of the possible sources of error in the fission counting, the chemical procedure, and the beta-counting (gas-phase proportional counter). A separate measurement of the yield ratio Xe-133/Kr-85 in U fission agreed closely with the same ratio computed from the absolute yield measurement above. As by-products of this work, we have found: 1) The independent yield of Xe-133 in U-235 fission is not greater than 0.1% of the 133 chain yield. 2) The independent yield of Xe-135 in U-235 fission is 3.5 (± 1.0) percent of the 135 chain yield. 3) The half-life of I-133 is 20.8 (± 0.2) hours. The Kr-85 and Xe-133 absolute yields in U-235 fission, together with the accurate relative yields of Kr and Xe …
Amplitude and Phase Functions for the Revised Parameters of the Cambridge Electron Accelerator
"The phase and amplitude functions describing the betatron oscillations in the synchrotron are calculated using the revised parameters of the Cambridge Electron Accelerator. The results are given numerically and plotted in a graph for one machine period."
The Aeolotropic Elastic Relations for Uranium Crystals
Handwritten report. This theoretical introduction to the anisotropic elastic properties of the orthorombic [sic] uranium crystal presents certain basic ideas which are useful in the study of experimental methods for determining preferred orientations in polycrystalline bodies. The method of analysis used to determine the elastic constants suggests explanations and correlations for the observations of sonic wave experiments on bars having preferred orientations and also serves as an introduction into the type of mathematical relations used in the study of anisotropic crystals.
Aerial Convention of October 13, 1919
The aerial convention delegates are listed as well as the set of rules that were developed during the session.
Aerial Gamma Ray and Magnetic Survey, Andalusia Quadrangle, Alabama: Final Report
A report regarding an aerial gamma-ray and magnetic survey of the Andalusia Quadrangle, Alabama
Aerial Gamma Ray and Magnetic Survey, Centerville Quadrangle, Iowa and Missouri: Final Report
A report regarding an aerial gamma-ray and magnetic survey of the Centerville Quadrangle, Iowa and Missouri
Aerial Gamma Ray and Magnetic Survey, Chicago Quadrangle, Indiana, Illinois, and Michigan: Final Report
Final report analyzing aerial gamma ray and magnetic data in the Chicago quadrangle, including a detailed geologic summary, interpretation report, reduced scale copies of all maps and profiles, histograms, and statistical tables for the quadrangle.
Aerial Gamma Ray and Magnetic Survey, Danville Quadrangle, Indiana and Illinois: Final Report
Final report analyzing aerial gamma ray and magnetic data in the Danville quadrangle, including a detailed geologic summary, interpretation report, reduced scale copies of all maps and profiles, histograms, and statistical tables for the quadrangle.
Aerial Gamma Ray and Magnetic Survey, Davenport Quadrangle, Iowa and Illinois: Final Report
Final report analyzing aerial gamma ray and magnetic data in the Davenport quadrangle, including a detailed geologic summary, interpretation report, reduced scale copies of all maps and profiles, histograms, and statistical tables for the quadrangle.
Aerial Gamma Ray and Magnetic Survey, Dothan Quadrangle, Georgia and Alabama: Final Report
A report regarding and aerial gamma-ray and magnetic survey of the Dothan Quadrangle, Georgia and Alabama
Aerial Gamma Ray and Magnetic Survey, Dubuque Quadrangle, Iowa, Illinois and Wisconsin: Final Report
Final report analyzing aerial gamma ray and magnetic data in the Dubuque quadrangle, including a detailed geologic summary, interpretation report, reduced scale copies of all maps and profiles, histograms, and statistical tables for the quadrangle.
Aerial Gamma Ray and Magnetic Survey, Final Report: Alexandria Quadrangle, Louisiana and Texas
This report provides radiometric and magnetic data for the Alexandria quadrangle between Louisiana and Texas that was acquired and processed in May and June of 1980. Appendix A provides a detailed summary of data acquisition, processing, interpretation, and presentation methods; Appendix B contains a flight summary report for the quadrangle.
Aerial Gamma Ray and Magnetic Survey, Final Report: Baton Rouge Quadrangle, Louisiana/Mississippi
Final report analyzing aerial gamma ray and magnetic data in the Baton Rouge quadrangle, including a detailed geologic summary, interpretation report, reduced scale copies of all maps and profiles, histograms, and statistical tables for the quadrangle.
Aerial Gamma Ray and Magnetic Survey, Final Report: Cincinnati Quadrangle, Indiana/Ohio/Kentucky
Final report analyzing aerial gamma ray and magnetic data in the Cincinnati quadrangle, including a detailed geologic summary, interpretation report, reduced scale copies of all maps and profiles, histograms, and statistical tables for the quadrangle.
Aerial Gamma Ray and Magnetic Survey, Final Report: Columbus Quadrangle, Ohio
Final report analyzing aerial gamma ray and magnetic data in the Columbus quadrangle, including a detailed geologic summary, interpretation report, reduced scale copies of all maps and profiles, histograms, and statistical tables for the quadrangle.
Aerial Gamma Ray and Magnetic Survey, Final Report: Des Moines Quadrangle, Iowa
Final report analyzing aerial gamma ray and magnetic data in the Des Moines quadrangle, including a detailed geologic summary, interpretation report, reduced scale copies of all maps and profiles, histograms, and statistical tables for the quadrangle.
Aerial Gamma Ray and Magnetic Survey, Final Report: Detroit Quadrangle, Michigan
Final report analyzing aerial gamma ray and magnetic data in the Detroit quadrangle, including a detailed geologic summary, interpretation report, reduced scale copies of all maps and profiles, histograms, and statistical tables for the quadrangle.
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