Degree Discipline

Degree Level

In-Situ Amelioration of Acid Mine Drainage Problems: Final Report (open access)

In-Situ Amelioration of Acid Mine Drainage Problems: Final Report

Final report
Date: May 1998
Creator: Brown, Terry H.
Object Type: Report
System: The UNT Digital Library
Conditioning and Hydration Reactions Associated With Clean Coal Technology Ash Disposal/Hydration: Final Report (open access)

Conditioning and Hydration Reactions Associated With Clean Coal Technology Ash Disposal/Hydration: Final Report

Final report
Date: June 1998
Creator: Bland, Alan E.
Object Type: Report
System: The UNT Digital Library
Miscible/Immiscible Gas Injection Processes: Final Report (open access)

Miscible/Immiscible Gas Injection Processes: Final Report

Final report
Date: March 1998
Creator: Fahy, L. J.; Mones, C. G.; Johnson, L. A., Jr. & Carlson, F. M.
Object Type: Report
System: The UNT Digital Library
Evaluation of Alternate Free Radical Initiators for Heavy Oil/Plastics Co-Processing: Final Report (open access)

Evaluation of Alternate Free Radical Initiators for Heavy Oil/Plastics Co-Processing: Final Report

Final report
Date: April 1998
Creator: Guffey, F. D. & Barbour, F. A.
Object Type: Report
System: The UNT Digital Library
Development of a Portable Data Acquisition System. Part 1: Development of a Portable Data Acquisition System (open access)

Development of a Portable Data Acquisition System. Part 1: Development of a Portable Data Acquisition System

Final report
Date: April 1998
Creator: Barbour, F. A.; Turner, T. F. & Carlson, F. M.
Object Type: Report
System: The UNT Digital Library
Haz-Flote: Ex-Situ Decontamination of Materials (open access)

Haz-Flote: Ex-Situ Decontamination of Materials

Final report
Date: April 1998
Creator: Brown, Terry H. & Bland, Alan E.
Object Type: Report
System: The UNT Digital Library
The SYNAG Process: Coal Combustion Ash Management Option (open access)

The SYNAG Process: Coal Combustion Ash Management Option

Final report
Date: June 1998
Creator: Bland, Alan E.
Object Type: Report
System: The UNT Digital Library
Process Support and Development for Compcoal: Final Report (open access)

Process Support and Development for Compcoal: Final Report

Final report
Date: March 1998
Creator: Merriam, Norman
Object Type: Report
System: The UNT Digital Library
COMPCOAL: A Profitable Process for Production of a Stable High-Btu Fuel From Powder River Basin Coal. Final Report (open access)

COMPCOAL: A Profitable Process for Production of a Stable High-Btu Fuel From Powder River Basin Coal. Final Report

Final report
Date: April 1998
Creator: Merriam, Norman W. & Turner, T. F.
Object Type: Report
System: The UNT Digital Library
Development of an On-Line Alkali Monitoring Probe: Final Report (open access)

Development of an On-Line Alkali Monitoring Probe: Final Report

Final report
Date: April 1998
Creator: Sethi, Vijay
Object Type: Report
System: The UNT Digital Library
Bench-Scale Testing and Verification of Pyrolysis Concept for Remediation of Tank Bottoms: Final Report (open access)

Bench-Scale Testing and Verification of Pyrolysis Concept for Remediation of Tank Bottoms: Final Report

Final report
Date: April 1998
Creator: Satchwell, Robert
Object Type: Report
System: The UNT Digital Library
Global Warming: A Northwest Perspective (open access)

Global Warming: A Northwest Perspective

The Northwest Power Planning Council convened a symposium in Olympia, Washington, on the subject of global climate change ( the greenhouse effect'') and its potential for affecting the Pacific Northwest. The symposium was organized in response to a need by the Power Council to understand global climate change and its potential impacts on resource planning and fish and wildlife planning for the region, as well as a need to understand national policy developing toward climate change and the Pacific Northwest's role in it. 40 figs., 15 tabs.
Date: February 1990
Creator: Scott, M. J. & Counts, C. A.
Object Type: Article
System: The UNT Digital Library
Advanced NMR-based techniques for pore structure analysis of coal (open access)

Advanced NMR-based techniques for pore structure analysis of coal

One of the main problems in coal utilization is the inability to properly characterize its complex pore structure. Coals typically have micro/ultra-micro pores but they also exhibit meso and macroporosity. We believe that measurement of the NMR parameters of various gas phase and adsorbed phase NMR active probes can provide the resolution to this problem. We will investigate the dependence of the common NMR parameters such as chemical shifts and relaxation times of several different nuclei and compounds on the pore structure of model microporous solids, carbons, and coals. In particular, we will study the interaction between several small molecules ({sup 129}Xe, {sup 3}He, {sup 2}H{sub 2}, {sup 14}N{sub 2}, {sup 14}NH{sub 3}, {sup 15}N{sub 2}, {sup 13}CH{sub 4}, {sup 13}CO{sub 2}) and the pore surfaces in coals. These molecules have been selected for their chemical and physical properties. A special NMR probe will be constructed which will allow the concurrent measurement of NMR properties and adsorption uptake at a variety of temperatures. All samples will be subjected to a suite of conventional'' pore structure analyses. These include nitrogen adsorption at 77 K with BET analysis, C0{sub 2} and CH{sub 4} adsorption at 273 K with D-R (Dubinin-Radushkevich) analysis, helium …
Date: January 1, 1992
Creator: Smith, D. M.
Object Type: Report
System: The UNT Digital Library
Enhancement of DIII-D neutral beam system for higher performance (open access)

Enhancement of DIII-D neutral beam system for higher performance

The DIII-D tokamak employs eight neutral beam systems for plasma heating and current drive experiments. These positive ion source neutral beam systems have gone through several improvements in operational technique and in system hardware since the start of conditioning of the first long pulse ion source in December 1986. These improvements have led to the routine operation in deuterium at beam power levels of 20 MW. The improvements in operational technique include filament power supply operating mode, accelerator grid voltage holding capability, mid changes in grid potential gradients. The hardware improvements include installation of arc notching, arc discharge density regulation, and control of neutralizer gas puffing. Each of these improvements are discussed in this paper. Successful testing and operation of the ion source at 93 kV deuterium beam energy, well above the design value of 80 kV, also led to the possibility of enhancing system capability to 28 MW power level, nearly twice the original design value. Upgrading of the beam system to 60 second pulse duration at the currently achieved power level is under consideration. Studies have shown that this pulse length extension can be achieved with improvements in beamline heat handling components and auxiliary systems, especially the power …
Date: September 1, 1992
Creator: Hong, R.; Colleraine, A. P.; Kellman, D. H.; Kim, J.; Luxon, J. L.; Nerem, A. et al.
Object Type: Article
System: The UNT Digital Library
Review of the US Department of Energy Classified Visits Program (open access)

Review of the US Department of Energy Classified Visits Program

This review examines the US Department of Energy (DOE) Classified Visits Program, which is administered by the Office of Safeguards and Security. The overall purpose of this analysis is to (1) ensure that DOE policy and implementing procedures are appropriate to maintain US national security intentions; (2) evaluate the effectiveness of the process used across the DOE complex; and (3) recommend changes which will enhance the overall efficiency of the process while maintaining the program's integrity.
Date: July 1, 1992
Creator: Martin, S. W.; Killinger, M. H. & Segura, M. A.
Object Type: Report
System: The UNT Digital Library
Run - Beyond - Cladding - Breach (RBCB) test results for the Integral Fast Reactor (IFR) metallic fuels program (open access)

Run - Beyond - Cladding - Breach (RBCB) test results for the Integral Fast Reactor (IFR) metallic fuels program

In 1984 Argonne National Laboratory (ANL) began an aggressive program of research and development based on the concept of a closed system for fast-reactor power generation and on-site fuel reprocessing, exclusively designed around the use of metallic fuel. This is the Integral Fast Reactor (IFR). Although the Experimental Breeder Reactor-II (EBR-II) has used metallic fuel since its creation 25 yeas ago, in 1985 ANL began a study of the characteristics and behavior of an advanced-design metallic fuel based on uranium-zirconium (U-Zr) and uranium-plutonium-zirconium (U-Pu-Zr) alloys. During the past five years several areas were addressed concerning the performance of this fuel system. In all instances of testing the metallic fuel has demonstrated its ability to perform reliably to high burnups under varying design conditions. This paper will present one area of testing which concerns the fuel system's performance under breach conditions. It is the purpose of this paper to document the observed post-breach behavior of this advanced-design metallic fuel. 2 figs., 1 tab.
Date: January 1, 1990
Creator: Batte, G. L. (Argonne National Lab., Idaho Falls, ID (USA)) & Hoffman, G. L. (Argonne National Lab., IL (USA))
Object Type: Article
System: The UNT Digital Library
Using the Tritium Plasma Experiment to evaluate ITER PFC safety. [Plasma-Facing Components] (open access)

Using the Tritium Plasma Experiment to evaluate ITER PFC safety. [Plasma-Facing Components]

The Tritium Plasma Experiment was assembled at Sandia National Laboratories, Livermore to investigate interactions between dense plasmas at low energies and plasma-facing component materials. This apparatus has the unique capability of replicating plasma conditions in a tokamak divertor with particle flux densities of 2 [times] 10[sup 19] ions/cm[sup 2] [center dot] s and a plasma temperature of about 15 eV using a plasma that includes tritium. With the closure of the Tritium Research Laboratory at Livermore, the experiment was moved to the Tritium Systems Test Assembly facility at Los Alamos National Laboratory. An experimental program has been initiated there using the Tritium Plasma Experiment to examine safety issues related to tritium in plasma-facing components, particularly the ITER divertor. Those issues include tritium retention and release characteristics, tritium permeation rates and transient times to coolant streams, surface modification and erosion by the plasma, the effects of thermal loads and cycling, and particulate production. A considerable lack of data exists in these areas for many of the materials, especially beryllium, being considered for use in ITER. Not only will basic material behavior with respect to safety issues in the divertor environment be examined, but innovative techniques for optimizing performance with respect to …
Date: January 1, 1993
Creator: Longhurst, G. R.; Anderl, R. A. (EG and G Idaho, Inc., Idaho Falls, ID (United States)); Bartlit, J. R. (Los Alamos National Lab., NM (United States)); Causey, R. A. (Sandia National Labs., Livermore, CA (United States)) & Haines, J. R. (MDC Aerospace, St. Louis, MO (United States))
Object Type: Article
System: The UNT Digital Library
Engineering, maintenance, and new initiatives to improve LAMPF beam availability and system reliability (open access)

Engineering, maintenance, and new initiatives to improve LAMPF beam availability and system reliability

Two different requirements are driving engineering studies and hardware development to improve LAMPF. The first is concerned with component and system improvements to increase beam availability during the LAMPF production cycle. Hardware changes in RF, power supplies, and magnets are being implemented to increase mean time between failure and reduce time to replace or repair failed units. A joint LAMPF-Industry project is on-going to improve reliability of RF components. A component test stand is being refurbished to include significant development capability. The second approach includes several changes that will increase the duty factor of the existing accelerator. Major changes are being evaluated for replacing the front end of the accelerator. Other changes improving high brightness capability could result in a new performance plateau for LAMPF.
Date: January 1, 1992
Creator: Harris, H. W.; DeHaven, R. A.; Hart, V. E.; Parsons, W. M. & Sturrock, J. C.
Object Type: Article
System: The UNT Digital Library
Modeling and sensitivity analysis study of the reduction of NO sub x by HNCO. [RAPRENOx process] (open access)

Modeling and sensitivity analysis study of the reduction of NO sub x by HNCO. [RAPRENOx process]

A chemical mechanism for the reduction of NO{sub x} by HNCO has been constructed to allow for the modeling of NO{sub x} in exhausts typical of natural gas combustion (RAPRENOx process). The reduction was modeled assuming plug flow, and either isothermal combustion or constant pressure adiabatic combustion. Variables were initial concentrations of NO, NO{sub 2}, CO, CH{sub 4}, H{sub 2}, and HNCO as well as initial temperatures. Exhaust residence time was nominally 1 s. Reduction was not achieved for prototypical natural gas exhaust'' for a reasonable residence time. Radical generation is crucial for reduction. H{sub 2} addition enhanced ignition and reduction. The final combustion temperature determines where NO{sub x} reduction ceases and NO{sub x} production increases. Reduction increases with HNCO, and breakthrough of NH{sub 3} and HNCO increses as well. N{sub 2}O production is due to NCO + NO, but the reduction of NO also occurs through reactions associated with the Thermal De-NOx chemistry. NH{sub 3} production and reactions are important to the reduction of NO. Sensitivity analysis under easy ignition conditions indicated that the same reactions involving nitrogen species, NH{sub 2} and NNH, important in De-NOx, are important when HNCO is used to reduce NO{sub x}. A real combustion …
Date: May 1, 1992
Creator: Brown, N. J. & Garay, J.
Object Type: Report
System: The UNT Digital Library
Spin structures of Fe/Gd and Fe/Cr multilayers determined by polarized neutron reflectometry (open access)

Spin structures of Fe/Gd and Fe/Cr multilayers determined by polarized neutron reflectometry

Polarized neutron reflection was used to determine the magnetic structure of two different antiferromagnetically coupled multilayer systems, Fe/Gd and Fe/Cr. In Fe/Gd, the Fe and Gd moments are coupled antiparallel at the interface. At low temperatures a surface induced magnetic phase transition was found. In Fe/Cr, annealing at temperatures of up to 425{degrees}C, resulted in the degrading of antiferromagnetic coupling between Fe layers and in the formation of ferromagnetically coupled regions.
Date: August 1, 1992
Creator: Loewenhaupt, M.; Hahn, W. (Forschungszentrum Juelich GmbH (Germany). Inst. fuer Festkoerperforschung); Huang, Y. Y.; Felcher, G. P. (Argonne National Lab., IL (United States)) & Parkin, S. S. P. (IBM Research Div., San Jose, CA (United States). Almaden Research Center)
Object Type: Article
System: The UNT Digital Library
Characterization of jet breakup mechanisms observed from simulant experiments of molten fuel penetrating coolant (open access)

Characterization of jet breakup mechanisms observed from simulant experiments of molten fuel penetrating coolant

The goal of this research program has been to add to our understanding of the breakup of molten fuel jets penetrating reactor coolant. Easily handled working fluids are used to simulate fuel jet breakup, so that detailed observations may be obtained from a relatively large number of experiments. The tools used for observing this behavior are high speed notion picture photography, Flash X-radiography, and X-ray cine. Jet breakup lengths are determined from motion pictures; the mechanisms by which the jets are fragmented may be inferred from radiographs.
Date: January 1, 1992
Creator: Jones, B. G.
Object Type: Report
System: The UNT Digital Library
Actuator system history of safety rod lower latch problems review of latch inspection video tapes (open access)

Actuator system history of safety rod lower latch problems review of latch inspection video tapes

During pre-restart testing the safety rod at position X26-YlO bound after being driven approximately two (2) feet out of the reactor. Subsequently, the rod was manually returned to it's seated position. Inspection of the lower latch showed that the latch locking plunger button (screwed on to the bottom of the plunger shaft and retained by a pin through a hole drilled through the button and the plunger shaft) was missing. The shaft failed through the hole drilled for the retaining pin. The button, with the retaining pin intact, was found lodged between the safety rod upper adapter collar and the top of the safety rod thimble top fitting. Analysis of the safety rod latch and accompanying forest guide tube design provided assurance that this type of failure would not cause binding during the scramming'' of the safety rods. Inspection of all of the K'' safety rod lower latches revealed six other latches with missing plunger buttons, and nine with other non-conformances which required latch replacement. A history search conducted by Reactor Engineering Design, Components Handling Group, is included in this report. The history search shows that latch design modifications, as a part of initial development of the latch system and …
Date: June 24, 1992
Creator: Banks, J. J.
Object Type: Report
System: The UNT Digital Library
Inhibition of retrogressive reactions in coal/petroleum co-processing (open access)

Inhibition of retrogressive reactions in coal/petroleum co-processing

The overall objective of this project is to develop a fundamental understanding of the reactions occurring at the onset of coke formation during the CO-processing of coals with action of chemical components, or groups of components, in coals and petroleum feedstocks to quantify and rank the effects of these components in retarding or enhancement of coke formation. The work involves bench scale reactions in microautoclaves, supplemented by studies of the carbonaceous residues by such techniques as diffuse reflectance Fourier transform infrared spectroscopy and {sup 13}C nuclear magnetic resonance spectrometry.
Date: May 1, 1992
Creator: Schobert, H. H. & Tomic, J.
Object Type: Report
System: The UNT Digital Library
Advanced radioactive waste-glass melters (open access)

Advanced radioactive waste-glass melters

During pilot scale operations of the Scale Glass Melter for the US Department of Energy a team of engineers and scientists was formed to assess the need for continued melter design development to support the Defense Waste Processing Facility (DWPF), and prioritize future efforts. Recently this has taken on new importance because of selection of the DWPF Melter design as the reference for the Hanford Waste Vitrification Project (HWVP), and increased interest at the West Valley Demonstration Project on melter life and replacement. Results of the study are summarized, and goals produced by the study are compared to the results of current programs at the Savannah River Laboratory (SRL).
Date: January 1, 1990
Creator: Bickford, D. F.
Object Type: Article
System: The UNT Digital Library