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Office of Scientific & Technical Information Technical Reports
14,060
Texas State Publications
386
USGS Topographic Map Collection
200
Texas Attorney General Opinions
150
Congressional Research Service Reports
146
Texas Register
119
Technical Report Archive and Image Library
106
Office of Technology Assessment
70
Federal Communications Commission Record
26
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13
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Texas Register
119
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104
Digital Raster Graphic Topographic Maps: 7.5 Minute Series (Topographic)
96
Texas Motor Vehicle Traffic Accident Summaries
40
Argonne National Laboratory Reports
37
74th Legislature of Texas
35
Report of investigations (United States. Bureau of Mines)
33
United States Bureau of Mines Reports
33
United States Geological Survey Reports
31
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26
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12 Batch coalescing studies
The purpose of the study was to identify and correct the problems in the 12 batch coalescing. The final goal is to be able to coalesce 12 booster batches of 11 bunches each into 12 bunches spaced at 21 buckets apart with an average intensity of 200 E9 ppb.
Date:
January 1, 1995
Creator:
Kourbanis, I. & Wildman, D.
Object Type:
Report
System:
The UNT Digital Library
222-S radioactive liquid waste line replacement and 219-S secondary containment upgrade, Hanford Site, Richland, Washington
The U.S. Department of Energy (DOE) is proposing to: (1) replace the 222-S Laboratory (222-S) radioactive liquid waste drain lines to the 219-S Waste Handling Facility (219-S); (2) upgrade 219-S by replacing or upgrading the waste storage tanks and providing secondary containment and seismic restraints to the concrete cells which house the tanks; and (3) replace the transfer lines from 219-S to the 241-SY Tank Farm. This environmental assessment (EA) has been prepared in compliance with the National Environmental Policy Act (NEPA) of 1969, as amended, the Council on Environmental Quality Regulations for Implementing the Procedural Provisions of NEPA (40 Code of Federal Regulations [CFR] 1500-1508), and the DOE Implementing Procedures for NEPA (10 CFR 1021). 222-S is used to perform analytical services on radioactive samples in support of the Tank Waste Remediation System and Hanford Site environmental restoration programs. Activities conducted at 222-S include decontamination of analytical processing and support equipment and disposal of nonarchived radioactive samples. These activities generate low-level liquid mixed waste. The liquid mixed waste is drained through pipelines in the 222-S service tunnels and underground concrete encasements, to two of three tanks in 219-S, where it is accumulated. 219-S is a treatment, storage, and/or disposal …
Date:
January 1, 1995
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
241-TX acoustic monitoring 114TX tank waste
This test will involve raising and lowering a sound transmitter in one low and receiver hydrophones in another low at 0.5 ft. intervals over a 12 ft. depth, which is the depth of the waste. The soundings are recorded by equipment outside the tank farm fence.
Date:
January 1, 1995
Creator:
Hurley, J. V.
Object Type:
Report
System:
The UNT Digital Library
384 Power plant waste water sampling and analysis plan
This document presents the 384 Power House Sampling and Analysis Plan. The Plan describes sampling methods, locations, frequency, analytes, and stream descriptions. The effluent streams from 384, were characterized in 1989, in support of the Stream Specific Report (WHC-EP-0342, Addendum 1).
Date:
January 1, 1995
Creator:
Hagerty, K. J. & Knotek, H. M.
Object Type:
Report
System:
The UNT Digital Library
1992-1993 Bonneville Appliance Efficiency Program: Showerhead evaluation. Volume I - report
The Bonneville Power Administration (Bonneville) provides wholesale electric power to over 100 retail distribution utilities in the Pacific Northwest. Bonneville is faced with meeting growing loads from these utilities. It acquires conservation as one means of meeting this load growth. Bonneville has offered a variety of conservation programs since 1980. Efficient showerheads have been a feature in residential conservation programs ever since. Bonneville launched the Residential Appliance Efficiency Program to focus on water-heater energy conservation opportunities in 1992. The Residential Appliance Efficiency Program consists of two parts, a water-heater efficiency program, and a hot-water efficiency program. This report evaluates the savings and costs of the first two years of the showerhead portion of the Residential Appliance Efficiency Program (the showerhead program). Although it is not a formal evaluation of the program limited to implementation or a {open_quotes}process{close_quotes} evaluation, observations about program design and implementation are included as appropriate. Results of this evaluation are limited to program participants within the Bonneville service territory.
Date:
January 1, 1995
Creator:
Warwick, W. M.
Object Type:
Report
System:
The UNT Digital Library
1992-1993 Bonneville Appliance Efficiency Program: Showerhead Evaluation Volume II - Appendices
This report included the appendices for 1992-1993 Bonneville appliance efficiency program: showerhead evaluation. It consists of nine appendices, titled: Bonneville documents; overview of research projects; Puget Power and Light persistence study; hot-water flow analyses and assumptions documentation; regional end-use metering program; showerhead and faucet aerator performance assessment; Bonneville showerhead program distribution methods by participating utility; water- and energy-saving measure distribution methods literature review; REMP study load shape results.
Date:
January 1, 1995
Creator:
Warwick, W. M.
Object Type:
Report
System:
The UNT Digital Library
1992--1993 low-temperature geothermal assessment program, Colorada
Previous assessments of Colorado`s low-temperature geothermal resources were completed by the Colorado Geological Survey in 1920 and in the mid- to late-1970s. The purpose of the 1992--1993 low-temperature geothermal resource assessment is to update the earlier physical, geochemical, and utilization data and compile computerized databases of the location, chemistry, and general information of the low-temperature geothermal resources in Colorado. The main sources of the data included published data from the Colorado Geological Survey, the US Geological Survey WATSTOR database, and the files of the State Division of Water Resources. The staff of the Colorado Geological Survey in 1992 and 1993 visited most of the known geothermal sources that were recorded as having temperatures greater than 30{degrees}C. Physical measurements of the conductivity, pH, temperature, flow rate, and notes on the current geothermal source utilization were taken. Ten new geochemical analyses were completed on selected geothermal sites. The results of the compilation and field investigations are compiled into the four enclosed Quattro Pro 4 databases. For the purposes of this report a geothermal area is defined as a broad area, usually less than 3 sq mi in size, that may have several wells or springs. A geothermal site is an individual well …
Date:
January 1, 1995
Creator:
Cappa, J. A. & Hemborg, H. T.
Object Type:
Report
System:
The UNT Digital Library
The 1992 Eruptions of Crater Peak Vent Mount Spurr Volcano, Alaska
A report which provides an overview of eruptions from Mount Spurr and the Alaska Volcano Observatory's response to them.
Date:
1995
Creator:
Keith, Terry E. C.
Object Type:
Report
System:
The UNT Digital Library
1994 Northern Goshawk inventory on portions of Los Alamos National Laboratory, Los Alamos, NM
Northern goshawks (Accipiter gentilis) (hereafter referred to as goshawk) are large forest dwelling hawks. They are the largest species of the Accipiter genus which also includes sharp-shinned hawks (A. striatus) and the Cooper`s hawk (A. cooperii). Goshawks are holarctic in distribution and nest in coniferous, deciduous, and mixed species forests. In the southwest they primarily nest in ponderosa pine (Pinus ponderosa), mixed species, and spruce-fir forests. Goshawks may be declining in population and reproduction in the southwestern United States. In 1982 the USDA-Forest Service listed the goshawk as a {open_quotes}sensitive species{close_quotes} and in 1992 the U.S. Fish and Wildlife Service listed the goshawk as a {open_quotes}Category 2 species{close_quotes} in accordance with the Endangered Species Act. Reasons for the possible decline in goshawk populations include timber harvesting resulting in the loss of nesting habitat, toxic chemicals, and the effects of drought, fire, and disease. Thus, there is a need to determine their population status and assess impacts of management activities in potential goshawk habitat. Goshawk inventory was conducted during the 1993 nesting season with no adult goshawk responses detected within the LANL survey area. As noted by Sinton and Kennedy, these results may be interpreted in several ways: (1) no goshawk …
Date:
January 1, 1995
Creator:
Sinton, D. T. & Kennedy, P. L.
Object Type:
Report
System:
The UNT Digital Library
1995 verification flow testing of the HDR reservoir at Fenton Hill, New Mexico
Recent flow testing of the Fenton Hill HDR reservoir has demonstrated that engineered geothermal systems can be shut-in for extended periods of d= with apparently no adverse effects. However, when this particular reservoir at Venton Hill was shut-in for 2 years in a pressurized condition, natural convection within the open-jointed reservoir region appears to have leveled out the preexisting temperature gradient so that the gradient has now approached a condition more typical of liquid-dominated hydrothermal reservoirs which air invariably almost isothermal due to natural convection. As a result of the sudden flow impedance reduction that led to an almost 50% increase in Production flow new the end of the Second Phase of the LTFR in May 1993, we were uncertain as to the state of the reservoir after being shut-in for 2 years. The flow performance observed during the current testing was found to be intermediate between that at-the end of the Second Phase of the LTFT and that following, the subsequent sudden flow increase, implying that whatever caused the sudden reduction in impedance in the first place is probably somehow associated with the cooldown of the reservoir near the injection interval, since temperature recovery at the surfaces of the …
Date:
January 1, 1995
Creator:
Brown, D.
Object Type:
Article
System:
The UNT Digital Library
1995 Waste Minimization Report Instructions and Forms
Reporting containing Waste Minimization Report forms for 1995 and instructions for filling these out. Includes examples of businesses that deal with hazardous waste and how they should fill out these forms, definitions for related terms, and codes for hazardous waste.
Date:
1995
Creator:
Texas Natural Resource Conservation Commission. Industrial and Hazardous Waste Division.
Object Type:
Report
System:
The Portal to Texas History
36th Annual Report
The ACIR Library is composed of publications that study the interactions between different levels of government. This document is an annual report.
Date:
January 1995
Creator:
United States. Advisory Commission on Intergovernmental Relations.
Object Type:
Book
System:
The UNT Digital Library
Absorption of Sparingly Soluble Gases by Reactive Media in Self-Aerated Gas-Liquid Contactors: A Scale-Up Procedure
Absorption of sparingly soluble gases, such as NO or O{sub 2}, is greatly enhanced if the latter react with the media. Among a dozen of reactive solvents for NO{sub x} abatement, aqueous acidic urea appears the most economically and environmentally attractive because urea is a cheap reagent and because products of reaction of urea with nitrous acid, formed in the liquid phase via absorption of NO and NO{sub 2}, are carbon dioxide and nitrogen, which can be directly released into the atmosphere. That makes urea process unique among other wet scrubbing processes that routinely produce secondary waste. Its full potential has never been realized, perhaps due to the lack of an efficient gas-liquid contactor to overcome low solubility of NO in aqueous solutions. LLNL has recently designed and built a bench scale gas-liquid contactor for nitric acid regeneration with oxygen. The contactor proved very effective in overcoming the problem of low solubility of oxygen converting back to nitric acid approximately 99% of nitrous acid formed at the cathode (which would otherwise convert to NO{sub x}). The bench scale contactor consists of a 12 inch diameter tank with self-inducting impeller/aerator of very high gas capacity. The aerator represents a 3.5 inch …
Date:
January 1995
Creator:
Zundelevich, Yury
Object Type:
Report
System:
The UNT Digital Library
Acceptance test procedure for the MO-294 Building
This supporting document provides the Acceptance Test Procedure (ATP) for the acceptance and testing of the fire alarm system of mobile office MO-294.
Date:
January 1, 1995
Creator:
McKenna, P. J.
Object Type:
Report
System:
The UNT Digital Library
Activation and Micropore Structure Determination of Carbon-Fiber Composite Molecular Sieves
The progress of research in the development of novel, rigid, monolithic adsorbent carbon fiber composites is described. Carbon fiber composites am produced at ORNL and activated at the CAER using steam or CO{sub 2} under different conditions, with the aims of producing a uniform degree of activation through the material, and of closely controlling pore structure and adsorptive properties. The principal focus of the work to date has been to produce materials with narrow porosity far use in gas separations. Carbon fiber composites are prepared at ORNL, usually in plate or tubular form, by vacuum molding from water slurries containing phenolic resin and chopped isotropic petroleum pitch fibers. The composites are activated at the CAER in steam or CO{sub 2} using samples of dimensions up to 1.5 x 4 x 12 cm that are cut from the original plates. One of the objectives is to produce uniformly activated composites, which is especially critical when attempting to active large monoliths. It has been found that there are appreciable variations in the density and permeability of the as-formed composites that must relate to the forming technique. These variations are expected to exert some influence on the rate and extent of reaction and …
Date:
January 1, 1995
Creator:
Jagtoyen, M.
Object Type:
Report
System:
The UNT Digital Library
Active core profile and transport modification by application of Ion Bernstein Wave power in PBX-M
Application of Ion Bernstein Wave Heating (IBWH) into the Princeton Beta Experiment-Modification (PBX-M) tokamak stabilizes sawtooth oscillations and generates peaked density profiles. A transport barrier, spatially correlated with the IBWH power deposition profile, is observed in the core of IBWH assisted neutral beam injection (NBI) discharges. A precursor to the fully developed barrier is seen in the soft x-ray data during edge localized mode (ELM) activity. Sustained IBWH operation is conducive to a regime where the barrier supports large {triangledown}n{sub e}, {triangledown}T{sub e}, {triangledown}v{sub phi}, and {triangledown}T{sub i}, delimiting the confinement zone. This regime is reminiscent of the H(high)-mode but with a confinement zone moved inwards. The core region has better than H-mode confinement while the peripheral region is L(low)-mode-like. The peaked profile enhanced NBI core deposition and increases nuclear reactivity. An increase in central T{sub i} results from {chi}{sub i} reduction (compared to H-mode) and better beam penetration. Bootstrap current fractions of up to 0.32--0.35 locally and 0.28 overall were obtained when an additional NBI burst is applied to this plasma.
Date:
January 1, 1995
Creator:
LeBlanc, B.; Bell, R. & Batha, S.
Object Type:
Report
System:
The UNT Digital Library
An Adaptive System for Process Control
Abstract: Researchers at the U.S. Bureau of Mines (USBM) have developed adaptive process control systems in which genetic algorithms (GA's) are used to augment fuzzy logic controllers (FLC's). GA's are search algorithms that rapidly locate near-optimum solutions to a wide spectrum of problems by loosely modeling the search procedures of natural genetics. FLC's are rule-based systems that efficiently manipulate a problem environment by modeling the "rule-of-thumb" strategy used in human decisionmaking. Together, GA's and FLC's include all of the capabilities necessary to produce powerful, efficient, and robust adaptive control systems. To perform efficiently, such control systems require a cont element to manipulate the problem environment, an analysis element to recognize changes in the problem environment, and an adaptive element to adjust to the changes in the problem environment. The control system also employs a computer simulation of the problem environment. Details of an overall adaptive control system are discussed. A specific laboratory acid-base pH system is used to demonstrate the ideas presented; all results are from the physical laboratory system and not from a computer simulation.
Date:
1995
Creator:
Karr, Charles L.; Gentry, E. J. & Stanley, D. A.
Object Type:
Report
System:
The UNT Digital Library
Adhesion of Diamond Films on Tungsten
The U.S. Bureau of Mines has investigated the chemical vapor deposition of diamond films on tungsten substrates. The effects of deposition parameters on the adhesion of the films was determined. The films were produced using a hot filament chemical vapor deposition system. Parameters investigated were substrate temperature and methane concentration in the feed gas. Film quality, morphology, and composition were characterized by scanning electron microscopy and Raman spectroscopy. Adhesion testing was performed using an indentation technique, and the results were quantified by relating adhesion to interface fracture toughness. Diamond films with well-faceted crystalline morphology with grain size greater than 1 pm had poor adhesion properties regardless of substrate temperature or methane concentration. Diamond films with smooth morphologies consisting of rounded clusters of small (<0.2 pm) diamond crystallites and amorphous carbon phases displayed much higher adhesion, although the conditions that led to the growth of these films are not understood.
Date:
1995
Creator:
Maggs, K. J.; Walkiewicz, J. W. & Clark, A. E.
Object Type:
Report
System:
The UNT Digital Library
Adsorption study for uranium in Rocky Flats groundwater
Six adsorbents were studied to determine their effectiveness in removing uranium in Rocky Flats groundwater. The bench column and batch (Kd) tests showed that uranium can be removed (>99.9%) by four adsorbents. Bone Charcoal (R1O22); F-1 Alumina (granular activated alumina); BIOFIX (immobilized biological agent); SOPBPLUS (mixed metal oxide); Filtrasorb 300 (granular activated carbon); and Zeolite (clinoptilolite).
Date:
January 1, 1995
Creator:
Laul, J. C.; Rupert, M. C.; Harris, M. J. & Duran, A.
Object Type:
Report
System:
The UNT Digital Library
Advanced Evaporator Technology Progress Report FY 1992
This report summarizes the work that was completed in FY 1992 on the program "Technology Development for Concentrating Process Streams." The purpose of this program is to evaluate and develop evaporator technology for concentrating radioactive waste and product streams such as those generated by the TRUEX process. Concentrating these streams and minimizing the volume of waste generated can significantly reduce disposal costs; however, equipment to concentrate the streams and recycle the decontaminated condensates must be installed. LICON, Inc., is developing an evaporator that shows a great deal of potential for this application. In this report, concepts that need to be incorporated into the design of an evaporator operated in a radioactive environment are discussed. These concepts include criticality safety, remote operation and maintenance, and materials of construction. Both solubility and vapor-liquid equilibrium data are needed to design an effective process for concentrating process streams. Therefore, literature surveys were completed and are summarized in this report. A model that is being developed to predict vapor phase compositions is described. A laboratory-scale evaporator was purchased and installed to study the evaporation process and to collect additional data. This unit is described in detail. Two new LICON evaporators are being designed for installation …
Date:
January 1995
Creator:
Chamberlain, D. B.
Object Type:
Report
System:
The UNT Digital Library
Advanced evaporator technology progress report FY 1992
This report summarizes the work that was completed in FY 1992 on the program {open_quotes}Technology Development for Concentrating Process Streams.{close_quotes} The purpose of this program is to evaluate and develop evaporator technology for concentrating radioactive waste and product streams such as those generated by the TRUEX process. Concentrating these streams and minimizing the volume of waste generated can significantly reduce disposal costs; however, equipment to concentrate the streams and recycle the decontaminated condensates must be installed. LICON, Inc., is developing an evaporator that shows a great deal of potential for this application. In this report, concepts that need to be incorporated into the design of an evaporator operated in a radioactive environment are discussed. These concepts include criticality safety, remote operation and maintenance, and materials of construction. Both solubility and vapor-liquid equilibrium data are needed to design an effective process for concentrating process streams. Therefore, literature surveys were completed and are summarized in this report. A model that is being developed to predict vapor phase compositions is described. A laboratory-scale evaporator was purchased and installed to study the evaporation process and to collect additional data. This unit is described in detail. Two new LICON evaporators are being designed for installation …
Date:
January 1, 1995
Creator:
Chamberlain, D.; Hutter, J. C. & Leonard, R. A.
Object Type:
Report
System:
The UNT Digital Library
Advanced light water reactor plants system 80+{trademark} design certification program. Annual progress report, October 1, 1993--September 30, 1994
The purpose of this report is to provide a status of the progress that was made towards Design Certification of System 80{sup +}{trademark} during the U.S. government`s 1994 fiscal year. The System 80+ Advanced Light Water Reactor (ALWR) is a 3931 MW (1350 MWe) Pressurized Water Reactor (PWR). The design covers an essentially complete plant. It is based on EPRI ALWR Utility Requirements Document (URD) improvements to the Standardized System 80 Nuclear Steam Supply System (NSSS) in operation at Palo Verde Units 1, 2 and 3. The NSSS is a traditional two-loop arrangement with two steam generators, two hot legs and four cold legs, each with a reactor coolant pump. The System 80+ standard design houses the NSSS in a spherical steel containment vessel which is enclosed in a concrete shield building, thus providing the safety advantages of a dual barrier to radioactivity release. Other major features include an all-digital, human-factors-engineered control room, an alternate electrical AC power source, an In-Containment Refueling Water Storage Tank (IRWST), and plant arrangements providing complete separation of redundant trains in safety systems. Some design enhancements incorporated in the System 80+ design are included in the four units currently under construction in the Republic of …
Date:
January 1, 1995
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Advanced Neutron Source (ANS) Project progress report, FY 1994
The President`s budget request for FY 1994 included a construction project for the Advanced Neutron Source (ANS). However, the budget that emerged from the Congress did not, and so activities during this reporting period were limited to continued research and development and to advanced conceptual design. A significant effort was devoted to a study, requested by the US Department of Energy (DOE) and led by Brookhaven National Laboratory, of the performance and cost impacts of reducing the uranium fuel enrichment below the baseline design value of 93%. The study also considered alternative core designs that might mitigate those impacts. The ANS Project proposed a modified core design, with three fuel elements instead of two, that would allow operation with only 50% enriched uranium and use existing fuel technology. The performance penalty would be 15--20% loss of thermal neutron flux; the flux would still just meet the minimum design requirement set by the user community. At the time of this writing, DOE has not established an enrichment level for ANS, but two advisory committees have recommended adopting the new core design, provided the minimum flux requirements are still met.
Date:
January 1, 1995
Creator:
Campbell, J. H.; King-Jones, K. H.; Selby, D. L.; Harrington, R. M. & Thompson, P. B.
Object Type:
Report
System:
The UNT Digital Library
Advanced neutron source materials surveillance program
The Advanced Neutron Source (ANS) will be composed of several different materials, one of which is 6061-T6 aluminum. Among other components, the reflector vessel and the core pressure boundary tube (CPBT), are to be made of 6061-T6 aluminum. These components will be subjected to high thermal neutron fluences and will require a surveillance program to monitor the strength and fracture toughness of the 6061-T6 aluminum over their lifetimes. The purpose of this paper is to explain the steps that were taken in the summer of 1994 toward developing the surveillance program. The first goal was to decide upon standard specimens to use in the fracture toughness and tensile testing. Second, facilities had to be chosen for specimens representing the CPBT and the reflector vessel base, weld, and heat-affected-zone (HAZ) metals. Third, a timetable had to be defined to determine when to remove the specimens for testing.
Date:
January 1, 1995
Creator:
Heavilin, S.M.
Object Type:
Report
System:
The UNT Digital Library