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Advanced Fuel Cell Development Progress Report: April-June 1983 (open access)

Advanced Fuel Cell Development Progress Report: April-June 1983

Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes efforts on development of molten carbonate fuel cells directed toward seeking alternative cathode materials to NiO. Based on an investigation of the thermodynamically stable phases formed under cathode conditions with a number of transition metal oxides, synthesis of prospective alternative cathode materials and doping of these materials to promote electronic conductivity is under way.
Date: February 1984
Creator: Ackerman, J. P. & Pierce, Robert Dean
System: The UNT Digital Library
[Appendix I-B. Petrographic Descriptions] (open access)

[Appendix I-B. Petrographic Descriptions]

Charts providing petrographic descriptions of rock samples obtained in the Waterloo Gulch drainage, listing the rock name, percentage of mineral components, and features of each rock.
Date: February 1984
Creator: Goodknight, Craig S. & Dixon, M.
System: The UNT Digital Library
[Appendix II-B. Petrographic Descriptions] (open access)

[Appendix II-B. Petrographic Descriptions]

Report describing the petrography of seven rhyolite specimens and one basalt specimen from China Hat, China Cap, and North Cone areas surveyed for the National Uranium Resource Evaluation (NURE) survey.
Date: February 1984
Creator: Goodknight, Craig S. & Allen, D. R.
System: The UNT Digital Library
[Appendix III-B. Petrographic Descriptions] (open access)

[Appendix III-B. Petrographic Descriptions]

Report presenting petrographic descriptions of five rock samples collected at or near the Pedad claims area surveyed for the National Uranium Resource Evaluation (NURE) survey, listing the rock name, percentage of mineral components, and features of each rock.
Date: February 1984
Creator: Goodknight, Craig S. & Dixon, M.
System: The UNT Digital Library
[Appendix IV-B. Petrographic Descriptions] (open access)

[Appendix IV-B. Petrographic Descriptions]

Report presenting petrographic descriptions of eleven rock samples collected at or near the Venado Creek area surveyed for the National Uranium Resource Evaluation (NURE) survey, listing the rock name, percentage of mineral components, and features of each rock.
Date: February 1984
Creator: Goodknight, Craig S.
System: The UNT Digital Library
[Appendix V-B. Petrographic Descriptions] (open access)

[Appendix V-B. Petrographic Descriptions]

Report presenting petrographic descriptions of eight rock samples collected at or near the Tusas Mountain Granite and Maquinita Granodorite areas surveyed for the National Uranium Resource Evaluation (NURE) survey, listing the rock name, percentage of mineral components, and features of each rock.
Date: February 1984
Creator: Goodknight, Craig S.
System: The UNT Digital Library
Aspen simulation of oil shale retort off-gas cleanup with venturi scrubbers (open access)

Aspen simulation of oil shale retort off-gas cleanup with venturi scrubbers

A significant fraction of the product energy from oil shale retorting is contained in the retort off gas. Most oil shale processes use the retort off gas from plant fuel. The H/sub 2/S and NH/sub 3/ in retort off gas produce too much SO/sub 2/ and NOX to allow burning without a pollution control system. We used the ASPEN flowsheet simulator to model retort off-gas cleanup by venturi scrubbers. Venturi scrubbers are commonly used to remove particulates from gas streams, but the scrubbing liquid also absorbs some NH/sub 3/ and H/sub 2/S from the gas. The ASPEN venturi scrubber model makes good predictions of the particulate removal efficiency. The ASPEN estimates for H/sub 2/S and NH/sub 3/ absorption are higher than the equilibrium absorption predictions made by a state-of-the-art sour water vapor-liquid equilibrium model, TIDES. The discrepancy probably results from trying to simulate an electrolyte system with a vapor-liquid equilibrium model that is designed for molecular systems. The simulation indicates that a venturi scrubber may absorb enough NH/sub 3/ to serve as the primary NH/sub 3/ removal system. The H/sub 2/S absorption is quite low, however, and some other process is needed to remove the H/sub 2/S. 17 references, 6 …
Date: February 1, 1984
Creator: Phillips, T. T.
System: The UNT Digital Library
Assessment of extent and degree of thermal damage to polymeric materials in the Three Mile Island Unit 2 reactor building. Volume VI (open access)

Assessment of extent and degree of thermal damage to polymeric materials in the Three Mile Island Unit 2 reactor building. Volume VI

Thermal damage to susceptible materials in accessible regions shows damage-distribution patterns that indicate nonuniform intensity of exposure. No clear explanation for nonuniformity is found in existing evidence; e.g., in some regions a lack of thermally susceptible materials frustrates analysis. Elsewhere, burned materials are present next to materials that seem similar but appear unscathed - leading to conjecture that the latter materials preferentially absorb water vapor during periods of high local steam concentration. Most of the polar crane pendant shows heavy burns on one half of its circumferential surface. This evidence suggests that the polar crane pendant side that experienced heaviest burn damage was exposed to intense radiant energy from a transient fire plume in the reactor containment volume. Tests and simple heat-transfer calculations based on pressure and temperature records from the accident show that the atmosphere inside the reactor building was probably 8% hydrogen in air, a value not inconsistent with the extent of burn damage. Burn-pattern geography indicates uniform thermal exposure in the dome volume to the 406-ft level (about 6 ft below the polar crane girder), partial thermal exposure in the volume between the 406- and 347-ft levels as indicated by the polar crane cable, and lack of …
Date: February 1, 1984
Creator: Alvares, N. J.
System: The UNT Digital Library
An Assessment of the Social and Special Effects of Siting a Low-Level Radioactive Waste Disposal Facility in Texas: Phase 1. Historical and Sociodemographic Dimensions (open access)

An Assessment of the Social and Special Effects of Siting a Low-Level Radioactive Waste Disposal Facility in Texas: Phase 1. Historical and Sociodemographic Dimensions

Report providing a background summary of the potential sitting areas for a low-level radioactive waste disposal facility and a thorough study of the possible site location.
Date: February 1984
Creator: Texas Low-Level Radioactive Waste Disposal Authority
System: The Portal to Texas History
Brine and gas recovery from geopressured systems. I. Parametric calculations (open access)

Brine and gas recovery from geopressured systems. I. Parametric calculations

A series of parametric calculations was run with the S-CUBED geopressured-geothermal simulator MUSHRM to assess the effects of important formation, fluid and well parameters on brine and gas recovery from geopressured reservoir systems. The specific parameters considered are formation permeability, pore-fluid salinity, temperature and gas content, well radius and location with respect to reservoir boundaries, desired flow rate, and possible shale recharge. It was found that the total brine and gas recovered (as a fraction of the resource in situ) were most sensitive to formation permeability, pore-fluid gas content, and shale recharge.
Date: February 1, 1984
Creator: Garg, S. K. & Riney, T. D.
System: The UNT Digital Library
Chemical Species of Migrating Radionuclides at Commercial Shallow Land Burial Sites Quarterly Progress Report October-December, 1983 Quarterly Progress Report October-December, 1983 (open access)

Chemical Species of Migrating Radionuclides at Commercial Shallow Land Burial Sites Quarterly Progress Report October-December, 1983 Quarterly Progress Report October-December, 1983

The primary purpose of this project is to develop an understanding of chemical processes that significantly influence the migration of radionuclides at commercial low-level waste (LLW} burial sites. Chemical measurements of waste trench leachate and identification of chanical changes in leachate during migration will provide a basis for geochemical waste transport models. This project will produce for the U.S. Nuclear Regulatory C011mission (NRC) information to support guidance for implementation of 10 CFR 61, particularly in the developnent of criteria for low level waste disposal site selection, management, permanent closure and monitoring. This project will also produce information needed by the Canmonwealth of Kentucky as they finalize plans to stabilize. close and monitor the Maxey Flats site.
Date: February 1, 1984
Creator: Kirby,, L. J.; RIckard,, W. H. & Toste,, A. P.
System: The UNT Digital Library
CO + H/sub 2/ reaction over nitrogen-modified iron catalysts. Quarterly technical progress report, October 1, 1983-December 30, 1983. [Denitriding of iron nitrides in both hydrogen and helium] (open access)

CO + H/sub 2/ reaction over nitrogen-modified iron catalysts. Quarterly technical progress report, October 1, 1983-December 30, 1983. [Denitriding of iron nitrides in both hydrogen and helium]

The synthesis of epsilon-Fe/sub 2.7/N is confirmed by Moessbauer spectroscopy. Carburization of epsilon-iron nitride for 2.5 hours in 3H/sub 2//CO at 523 K starts the formation of a bulk structure similar to that seen during ..gamma..'-iron nitride carburization. Reaction of ..gamma..'-Fe/sub 4/N in 3CO/H/sub 2/ synthesis gas at 523 K shows a better bulk stability than reaction in 3H/sub 2//CO. Kinetic analysis of the product distribution at the higher CO ratio confirms greater activity and selectivity maintainance. The kinetics of denitriding in both He and H/sub 2/ was studied with a mass spectrometer. Extremely rapid nitrogen loss was observed from both ..gamma..'-Fe/sub 4/N and epsilon-Fe/sub 2.7/N catalysts in H/sub 2/ at 523 K. In both cases a initial exposure to H/sub 2/ produced a significant amount of NH/sub 3/ which we ascribe to an active surface species. Hydrogenation of the bulk continued with a slow rise to a maximum about 90 seconds after the introduction of H/sub 2/. The denitriding activity of the epsilon-Fe/sub 2.7/N catalyst was significantly higher than that of the ..gamma..'-Fe/sub 4/N catalyst. In contrast, the denitriding rate of epsilon-Fe/sub 2.7/N in He was significantly slower than that in H/sub 2/ until high temperatures (773K) were reached. …
Date: February 1, 1984
Creator: Delgass, W.N.
System: The UNT Digital Library
Commercial waste treatment program annual progress report for FY 1983 (open access)

Commercial waste treatment program annual progress report for FY 1983

This annual report describes progress during FY 1983 relating to technologies under development by the Commercial Waste Treatment Program, including: development of glass waste form and vitrification equipment for high-level wastes (HLW); waste form development and process selection for transuranic (TRU) wastes; pilot-scale operation of a radioactive liquid-fed ceramic melter (LFCM) system for verifying the reliability of the reference HLW treatment proces technology; evaluation of treatment requirements for spent fuel as a waste form; second-generation waste form development for HLW; and vitrification process control and product quality assurance technologies.
Date: February 1, 1984
Creator: McElroy, J.L. & Burkholder, H.C. (comps.)
System: The UNT Digital Library
Comparative Studies on the Carbohydrate Composition of Marine Macroalgae: An Annotated Bibliography (open access)

Comparative Studies on the Carbohydrate Composition of Marine Macroalgae: An Annotated Bibliography

An annotated bibliography of journal articles related to comparative studies on the carbohydrate composition of marine macroalgae produced for the Solar Energy Research Institute (SERI).
Date: February 1, 1984
Creator: Mack, R. W.
System: The UNT Digital Library
Control of respirable particles and radon progeny with portable air cleaners (open access)

Control of respirable particles and radon progeny with portable air cleaners

Eleven portable air cleaning devices have been evaluated for control of indoor concentrations of respirable particles and radon progeny. Following injection of cigarette smoke and radon in a room-size chamber, decay rates for particles and radon progeny concentrations were measured with and without air cleaner operation. Particle concentrations were obtained for total number concentration and for number concentration by particle size. In tests with no air cleaner the natural decay rate for cigarette smoke was observed to be 0.2 hr/sup -1/. Air cleaning rates for particles were found to be negligible for several small panel-filters, a residential ion-generator, and a pair of mixing fans. The electrostatic precipitators and extended surface filters tested had significant particle removal rates, and a HEPA-type filter was the most efficient air cleaner. The evaluation of radon progeny control produced similar results; the air cleaners which were effective in removing particles were also effective in removing radon progeny. At low particle concentrations plateout of the unattached radon progeny is an important removal mechanism. Based on data from these tests, the plateout rate for unattached progeny was found to be 15 hr/sup -1/. The unattached fraction and the overall removal rate due to deposition of attached and …
Date: February 1, 1984
Creator: Offermann, F.J.; Sextro, R.G.; Fisk, W.J.; Nazaroff, W.W.; Nero, A.V.; Revzan, K.L. et al.
System: The UNT Digital Library
Costs to build Fermilab in 1984 dollars (open access)

Costs to build Fermilab in 1984 dollars

It is of current interest to examine the costs incurred to date to build Fermi National Accelerator Laboratory and to determine what those costs are when stated in FY 1984 constant dollars. The appended tables are in support of this exercise and are based on all costs for Equipment items (reduced by obsolescence) and all Plant Projects which have been appropriated through FY 1984. Also included are non-plant costs which are required to complete the Energy Saver, Tevatron I and II projects (i.e., Equipment and R and D in support of Construction). This study makes the assumption that all funding through FY 1984 will have been costed by the end of FY 1986. Those costs incurred in FY 1985 and FY 1986 have been deflated to FY 1984 dollars. See Appendix A for the DOE inflation factors used in the conversion to FY 1984 dollars. The costs are identified in three categories. The Accelerator Facilities include all accelerator components, the buildings which enclose them and utilities which support them. The Experimental Facilities include all beam lines, enclosures, utilities and experimental equipment which are usable in current experimental programs. The Support Facilities include lab and office space, shops, assembly facilities, roads, …
Date: February 1, 1984
Creator: Jordan, N. G. & Livdahl, P. V.
System: The UNT Digital Library
Criticality experiments with low enriched UO/sub 2/ fuel rods in water containing dissolved gadolinium (open access)

Criticality experiments with low enriched UO/sub 2/ fuel rods in water containing dissolved gadolinium

The results obtained in a criticality experiments program performed for British Nuclear Fuels, Ltd. (BNFL) under contract with the United States Department of Energy (USDOE) are presented in this report along with a complete description of the experiments. The experiments involved low enriched UO/sub 2/ and PuO/sub 2/-UO/sub 2/ fuel rods in water containing dissolved gadolinium, and are in direct support of BNFL plans to use soluble compounds of the neutron poison gadolinium as a primary criticality safeguard in the reprocessing of low enriched nuclear fuels. The experiments were designed primarily to provide data for validating a calculation method being developed for BNFL design and safety assessments, and to obtain data for the use of gadolinium as a neutron poison in nuclear chemical plant operations - particularly fuel dissolution. The experiments program covers a wide range of neutron moderation (near optimum to very under-moderated) and a wide range of gadolinium concentration (zero to about 2.5 g Gd/l). The measurements provide critical and subcritical k/sub eff/ data (1 greater than or equal to k/sub eff/ greater than or equal to 0.87) on fuel-water assemblies of UO/sub 2/ rods at two enrichments (2.35 wt % and 4.31 wt % /sup 235/U) and …
Date: February 1, 1984
Creator: Bierman, S. R.; Murphy, E. S.; Clayton, E. D. & Keay, R. T.
System: The UNT Digital Library
Depolarization of D-T plasmas by recycling in material walls (open access)

Depolarization of D-T plasmas by recycling in material walls

The feasibility of using polarized deuterium (D) and tritium (T) plasmas in fusion reactors may be seriously affected by recycling in material walls. Theoretical and experimental results are reviewed which show how the depolarization rates of absorbed D and T depend on first wall parameters such as the temperature, the bulk and surface diffusivities, the density of electronic states at the Fermi surface, the spectral density of microscopic fluctuating electric field gradients, and the concentration of paramagnetic impurities. Nuclear magnetic resonance (NMR) spectroscopy of hydrogenated and deuterated amorphous semiconductors suggests that low-Z nonmetallic materials may provide a satisfactory first wall or limiter coating under reactor conditions with characteristic depolarization times of several seconds. Experiments are proposed to test the consequences of our analysis.
Date: February 1, 1984
Creator: Greenside, H. S.; Budny, R. V. & Post, D. E.
System: The UNT Digital Library
Design and operation of a passive neutron monitor for assaying the TRU content of solid wastes (open access)

Design and operation of a passive neutron monitor for assaying the TRU content of solid wastes

A passive neutron monitor has been designed and built for determining the residual transuranic (TRU) and plutonium content of chopped leached fuel hulls and other solid wastes from spent Fast Flux Test Facility (FFTF) fuel. The system was designed to measure as little as 8 g of plutonium or 88 mg of TRU in a waste package as large as a 208-l drum which could be emitting up to 220,000 R/hr of gamma radiation. For practical purposes, maximum assay times were chosen to be 10,000 sec. The monitor consists of 96 /sup 10/BF/sub 3/ neutron sensitive proportional counting tubes each 5.08 cm in diameter and 183 cm in active length. Tables of neutron emission rates from both spontaneous fission and (..cap alpha..,n) reactions on oxygen are given for all contributing isotopes expected to be present in spent FFTF fuel. Tables of neutron yeilds from isotopic compositions predicted for various exposures and cooling times are also given. Methods of data reduction and sources, magnitude, and control of errors are discussed. Backgrounds and efficiencies have been measured and are reported. A section describing step-by-step operational procedures is included. Guidelines and procedures for quality control and troubleshooting are also given. 13 references, 15 …
Date: February 1, 1984
Creator: Brodzinski, R.L.; Brown, D.P.; Rieck, H.G. Jr. & Rogers, L.A.
System: The UNT Digital Library
Design of a photovoltaic central power station (open access)

Design of a photovoltaic central power station

Photovoltaic central power station designs have been developed for both high-efficiency flat-panel arrays and two-axis tracking concentrator arrays. Both designs are based on a site adjacent to the Saguaro Power Station of Arizona Public Service. The plants are 100 MW each, made of 5 MW subfields. The site specific designs allow detailed cost estimate for site preparation, installation, and engineering. These designs are summarized and cost estimates analyzed. Provided also are recommendations for future work to reduce system cost for each plant design.
Date: February 1, 1984
Creator: unknown
System: The UNT Digital Library
Design of a photovoltaic central power station: flat-plate array (open access)

Design of a photovoltaic central power station: flat-plate array

A design for a photovoltaic central power station using fixed flat-panel arrays has been developed. The 100 MW plant is assumed to be located adjacent to the Saguaro Power Station of Arizona Public Service. The design assumes high-efficiency photovoltaic modules using dendritic web cells. The modules are arranged in 5 MW subfields, each with its own power conditioning unit. The photovoltaic output is connected to the existing 115 kV utility switchyard. The site specific design allows detailed cost estimates for engineering, site preparation, and installation. Collector and power conditioning costs have been treated parametrically.
Date: February 1, 1984
Creator: unknown
System: The UNT Digital Library
Design of photovoltaic central power station concentrator array (open access)

Design of photovoltaic central power station concentrator array

A design for a photovoltaic central power station using tracking concentrators has been developed. The 100 MW plant is assumed to be located adjacent to the Saguaro Power Station of Arizona Public Service. The design assumes an advanced Martin Marietta two-axis tracking fresnel lens concentrator. The concentrators are arrayed in 5 MW subfields, each with its own power conditioning unit. The photovoltaic plant output is connected to the existing 115 kV switchyard. The site specific design allows detailed cost estimates for engineering, site preparation, and installation. Collector and power conditioning costs have been treated parametrically.
Date: February 1, 1984
Creator: unknown
System: The UNT Digital Library
Design study of the TeV I pulsed septum magnet (open access)

Design study of the TeV I pulsed septum magnet

Magnetic field calculations have been performed using the POISSON code to assist in the design of a pulsed septum magnet for beam manipulation in the TeV I antiproton accumulator/debuncher system. Magnet current distributions are obtained from eddy current considerations relative to a pulsed half-sine wave of 1200 Hz. Magnet end effects are not considered here.
Date: February 1, 1984
Creator: Oleksiuk, L.W.
System: The UNT Digital Library
Development of metallization process: FSA project, cell and module formation research area. Quarterly technical progress report for the period ending December 31, 1983 (open access)

Development of metallization process: FSA project, cell and module formation research area. Quarterly technical progress report for the period ending December 31, 1983

New pastes were evaluated that contained additives to aid in the silicon-to-metallization contact. None were completely successful, however, inks containing silver-organic compounds showed promise.
Date: February 1, 1984
Creator: Garcia, A. III
System: The UNT Digital Library