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A 10 um Resolution Secondary Emission Monitor for Fermilab's Targeting Station
Improvement in focusing the proton beam onto the antiproton production target necessitates the development of a higher resolution beam profile monitor. Two designs for the construction of a multiwire profile mointor grid are presented. The first is a conventional strung and tensioned Ti wire design. The second is a photo etched Ti grid of wires bonded to a ceramic substrate. Both have a central wire spacing of 125 {mu}m. The completed beam profile monitors are designed to operate in a 120 GeV beam pulse of 5 x 10{sup 12} protons with a 1.5{mu}s duration and will be installed in late 1993.
Date:
January 1, 1994
Creator:
Hurh, P.; O'Day, S.; Dombrowski, R. & Page, T.
Object Type:
Report
System:
The UNT Digital Library
900-mW average power and tunability from a diode-pumped 2.94-{mu}m Er:YAG oscillator
In this paper, the authors report on a diode-side-pumped Er:YAG laser that generates over 500 mW of average power at 2.94 {mu}m, and tunes over a 6 nm range centered about the 2.94-{mu}m transition. Prior to the development of the laser, diode-pumped Er:YAG lasers have been end-pumped monolithic devices that deliver {approximately}200 mW of output at 2.94 {mu}m. Much of the difficulty in obtaining higher average power from Er:YAG stems from the unfavorable lifetimes of the upper and lower laser levels, the complex state dynamics, and a low stimulated emission cross section ({sigma} {approx} 3 {times} 10{sup {minus}20} cm{sup 2}). One of the most important dynamical processes in Er:YAG is cross relaxation between neighboring Er{sup 3+} ions in the {sup 4}I{sub 13/2} level. By recycling much of the {sup 4}I{sub 13/2} population (lower laser level) into {sup 4}I{sub 11/2} (upper laser level), the cross relaxation overcomes the unfavorable lifetimes of the two levels, allowing the population inversion to be sustained. It is this cross relaxation along with thermalization of the two laser levels that allows cw oscillation on the 2.94 {mu}m line to take place. The laser that they describe here is a quasi-cw device as the approach to obtaining …
Date:
January 1, 1994
Creator:
Hamilton, C. E.; Beach, R. J.; Sutton, S. B.; Furu, L. & Krupke, W. F.
Object Type:
Article
System:
The UNT Digital Library
Accelerated clean-up at the Hanford Site
The Hanford Site began operations in 1943 as one of the sites for plutonium production associated with the Manhattan Project. It has been used, in part, for nuclear reactor operation, reprocessing of spent fuel, and management of radioactive waste. The Hanford Site covers approximately 1,434 km{sup 2} (560 mi{sup 2}2) in southeastern Washington State. The subject of this paper, the 618-9 Burial Ground, is located on the Hanford Site approximately 1.6 km (1 mi) west of the Columbia River, and a few miles north of Richland, Washington. Throughout Hanford Site history, prior to legislation regarding disposal of chemical waste products, some chemical waste byproducts were disposed ,ia burial in trenches. One such trench was the 618-9 Burial Ground. This burial ground was suspected to contain approximately 19,000 L (5,000 gal) of uranium-contaminated organic solvent, disposed in standard 55-gal (208-L) metal drums. The waste was produced from research and development activities related to fuel reprocessing.
Date:
January 1, 1994
Creator:
Frain, J. M. & Johnson, W. L.
Object Type:
Article
System:
The UNT Digital Library
Accelerated Decontamination and Decommissioning at the Hanford Site
The Hanford Site has over 100 facilities that have been declared surplus and are scheduled to be decommissioned. In addition to these surplus facilities, there is a significant number of facilities that are currently being shut down, deactivated, and transferred to the Decontamination and Decommissioning (D&D) program. In the last year, Westinghouse Hanford Company and the US Department of Energy, Richland Operations Office, have developed and implemented an initiative to accelerate the D&D work at the Hanford Site. The strategy associated with accelerated D&D is to reduce the number of surplus facilities, eliminate potential safety hazards, demonstrate meaningful cleanup progress, and recycle materials for other uses. This initiative has been extremely successful and has resulted in the safe demolition of 13 facilities in fiscal year (FY) 1993. In addition, four facilities have been completed in FY 1994 and demolition of several other facilities is currently underway.
Date:
January 1, 1994
Creator:
Hughes, M. C.; Douglas, L. M. & Marske, S. G.
Object Type:
Article
System:
The UNT Digital Library
Accelerated screening methods for predicting lubricant performance in refrigerant compressors. Progress report, May 1, 1993--December 31, 1993
As part of an overall testing program to identify more effective bench testers for screening oils for compressors, a comparison is made in this report between data obtained from a Falex specimen tester and those obtained from a high pressure tribometer (HPT). The Falex data were supplied by three compressor manufacturers. These data were mainly obtained by bubbling refrigerants through the oil, whereas, the data from the HPT are based on environmental (temperature and pressure) found in specific contacts in compressors. The same contact geometries and materials are used for both the Falex and the HPT tests. The main purpose of this comparison is to see if the controlled environment and the lower loads used with the HPT produces different rankings than that obtained from the Falex tests. In general, the results obtained from the HPT did not always correlate with each other and those obtained from the Falex tester. These findings are discussed in detail in this report.
Date:
January 1, 1994
Creator:
Cusano, C.
Object Type:
Report
System:
The UNT Digital Library
Accident safety analysis for 300 Area N Reactor Fuel Fabrication and Storage Facility
The purpose of the accident safety analysis is to identify and analyze a range of credible events, their cause and consequences, and to provide technical justification for the conclusion that uranium billets, fuel assemblies, uranium scrap, and chips and fines drums can be safely stored in the 300 Area N Reactor Fuel Fabrication and Storage Facility, the contaminated equipment, High-Efficiency Air Particulate filters, ductwork, stacks, sewers and sumps can be cleaned (decontaminated) and/or removed, the new concretion process in the 304 Building will be able to operate, without undue risk to the public, employees, or the environment, and limited fuel handling and packaging associated with removal of stored uranium is acceptable.
Date:
January 1, 1994
Creator:
Johnson, D. J. & Brehm, J. R.
Object Type:
Report
System:
The UNT Digital Library
Actinide recovery techniques utilizing electromechanical processes
Under certain conditions, the separation of actinides using electromechanical techniques may be an effective means of residue processing. The separation of granular mixtures of actinides and other materials discussed in this report is based on appreciable differences in the magnetic and electrical properties of the actinide elements. In addition, the high density of actinides, particularly uranium and plutonium, may render a simultaneous separation based on mutually complementary parameters. Both high intensity magnetic separation and electrostatic separation have been investigated for the concentration of an actinide waste stream. Waste stream constituents include an actinide metal alloy and broken quartz shards. The investigation of these techniques is in support of the Integral Fast Reactor (IFR) concept currently being developed at Argonne National Laboratory under the auspices of the Department of Energy.
Date:
January 1, 1994
Creator:
Westphal, B. R. & Benedict, R. W.
Object Type:
Article
System:
The UNT Digital Library
Activation of the liquid helium contamination during its passage in the Collider ring
Radioactivation of possible contamination of the liquid helium trapped in the arcs of the Collider ring of the Superconducting Super Collider and transported by the liquid helium is estimated. This estimation is used to calculate the dose rate on the filter of the refrigerator plant located at the top of the shaft.
Date:
January 1, 1994
Creator:
Lopez, G.
Object Type:
Report
System:
The UNT Digital Library
Adaptation of a commercial robot for genome library replication
This report describes tools and fixtures developed at the Human Genome Center at Lawrence Berkeley Laboratory for the Hewlett-Packard ORCA{trademark} (Optimized Robot for Chemical Analysis) to replicate large genome libraries. Photographs and engineering drawings of the various custom-designed components are included.
Date:
January 1, 1994
Creator:
Uber, D. C. & Searles, W. L.
Object Type:
Report
System:
The UNT Digital Library
Addendum to the corrective action plan for Underground Storage Tanks 1219-U, 1222-U, 2082-U, 2068-U at the Rust Garage Facility, Buildings 9720-15 and 9754-1: Oak Ridge Y-12 Plant, Oak Ridge, Tennessee, Facility ID {number_sign}0-010117
This document represents an addendum to the Corrective Action Plan (CAP) for underground storage tanks 1219-U, 2082-U, and 2068-U located at Buildings 9720-15 and 9754-1, Oak Ridge Y-12 Plant, Oak Ridge, TN. The site of the four underground storage tanks is commonly referred to as the Rust Garage Facility. The original CAP was submitted to the Tennessee Department of Environment and Conservation (TDEC) for review in May 1992. During the time period after submission of the original CAP for the Rust Garage Facility, Y-12 Plant Underground Storage Tank (UST) Program personnel continued to evaluate improvements that would optimize resources and expedite the activities schedule presented in the original CAP. Based on these determinations, several revisions to the original corrective action process options for remediation of contaminated soils are proposed. The revised approach will involve excavation of the soils from the impacted areas, on-site thermal desorption of soil contaminants, and final disposition of the treated soils by backfilling into the subject site excavations. Based on evaluation of the corrective actions with regard to groundwater, remediation of groundwater under the Y-12 Plant CERCLA Program is proposed for the facility.
Date:
January 1, 1994
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Advanced gas turbine systems research. Quarterly report, October--December, 1993
This is a report on the technical progress of the advanced gas turbine systems research program. The second Request for Proposals (RFP 94-01) was issued at the end of November. Research areas were restricted somewhat compared with the initial RFP, as the Industrial Review Board wished to concentrate on the highest priority technologies. Performing Members now number 61, with another four universities expressing interest in joining. Development of the Materials Technology area of the ATS program is proceeding, with resolution expected in early 1994 to support issuing solicitations by the summer. The first AGTSR workshop has been scheduled for late February in Nashville to discuss combustion modeling.
Date:
January 1, 1994
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Advanced thermally stable jet fuels. Technical progress report, October 1993--December 1993
The Penn State program in advancd thermally stable coal-based jet fuels has five broad objectives: (1) development of mechanisms of degradation and solids formation; (2) quantitative measurement of growth of sub-micrometer and micrometer-sized particles suspended in fuels during thermal stressing; (3) characterization of carbonaceous deposits by various instrumental and microscopic methods; (4) elucidation of the role of additives in retarding them formation of vcarbonaceous solids; and, (5) assessment of the potential of production of high yields of cycloalkanes by direct liquefaction of coal.
Date:
January 1, 1994
Creator:
Schobert, H. H.; Eser, S.; Song, C.; Hatcher, P. G.; Walsh, P. M. & Coleman, M. M.
Object Type:
Report
System:
The UNT Digital Library
Advanced tokamak research on the DIII-D tokamak
The objective of the planned research in advanced tokamak development on DIII-D at General Atomics, San Diego, USA. is to establish improved tokamak operation through significant improvements in the stability factor, confinement quality, and bootstrap current fraction using localized radio frequency (rf) current profile control, rf and neutral beam heating for pressure profile control, as well as control of plasma rotation and optimization of the plasma boundary conditions. Recent research results in H-mode confinement, modifications of current profiles to achieve higher confinement and higher {beta}, a new regime of improved confinement (VH-mode), and rf noninductive current drive are encouraging. In this talk, arguments will be presented supporting the need for improved performance in tokamak reactors. Experimentally observed advanced performance regimes on DIII-D will be discussed. Confinement improvement up to H = 4, where H is the ratio of energy confinement time to the ITER89-P scaling H{triple_bond} {Tau}{sub E}/{Tau}{sub E-ITER89-P}, has been achieved. In other discharges {beta}{sub N} = {beta}/(I/aB),[%-m{center_dot}{Tau}/MA] {approx_gt} 6 has been obtained. These values have so far been achieved transiently and independently. Techniques, will be described which can extend the high performance to quasi-steady-state and sustain the high H and {beta}{sub N} values simultaneously. Two high performance regimes, …
Date:
January 1, 1994
Creator:
Chan, V. S.
Object Type:
Article
System:
The UNT Digital Library
Advanced turbine systems program: Conceptual design and product development. Topical report, November 1993
This report has been prepared by Solar Turbines Incorporated (Solar) in accordance with Task 2 of the Advanced Turbine Systems (ATS) Contract. This report addresses only the work that will be performed under Task 8 (Design and Test of Critical Components) of the Contract. The discussion is divided into four general sections: Project Description; Potential Environmental Impacts; Required Permits and Licenses; and Environmental, Safety and Health (ES and H) Agency Contact Information. As described in further detail herein, the activities to occur during the project (i.e., Task 8) consists primarily of short duration testing of laboratory-scale components (or portions of components) for the ATS program. The testing involved will fall in the following general categories: recuperator, combustor, and blade/airfoil cooling. All activities contemplated will occur at existing facilities. Solar believes that the information in this report supports the conclusion that no significant environmental impacts will be associated with the project.
Date:
January 1, 1994
Creator:
Wilken, L. S.
Object Type:
Report
System:
The UNT Digital Library
Aerosol optical depth derived from solar radiometry observations at northern mid-latitude sites
Routine, automated solar radiometry observations began with the development of the Mobile Automated Scanning Photometer (MASP) and its installation at the Rattlesnake Mountain Observatory (RMO). We have introduced a microprocessor controlled rotating shadowband radiometer (RSR), both the single detector and the multi-filter/detector (MFRSR) versions to replace the MASP. The operational mode of the RSRs is substantially different than the MASP or other traditional sun-tracking radiometers, because, by virtue of the automated rotating shadowband, the total and diffuse irradiance on a horizontal plane are measured and the direct-normal component deduced through computation from the total and diffuse components by the self-contained microprocessor. Because the three irradiance components are measured using the same detector for a given wavelength, the calibration coefficients are identical for each component, thus reducing errors when comparing them. The MFRSR is the primary radiometric instrument in the nine-station Quantitative Links Network (QLN) established in the eastern United States in late 1991. Data from this network are being used to investigate how cloud- and aerosol-induced radiative effects vary in time and with cloud structure and type over a mid-latitude continental region. This work supports the DOE Quantitative Links Program to quantify linkages between changes in atmospheric composition and climate …
Date:
January 1, 1994
Creator:
Laulainen, N. S.; Larson, N. R.; Michalsky, J. J. & Harrison, L. C.
Object Type:
Article
System:
The UNT Digital Library
AFDM: An advanced fluid-dynamics model. Volume 6: EOS-AFDM interface
This volume of the Advanced Fluid-Dynamics Model (AFDM) documents the modeling of the equation of state (EOS) in the code. The authors present an overview of the basic concepts underlying the thermodynamics modeling and resulting EOS, which is a set of relations between the thermodynamic properties of materials. The AFDM code allows for multiphase-multimaterial systems, which they explore in three phase models: two-material solid, two-material liquid, and three-material vapor. They describe and compare two ways of specifying the EOS of materials: (1) as simplified analytic expressions, or (2) as tables that precisely describe the properties of materials and their interactions for mechanical equilibrium. Either of the two EOS models implemented in AFDM can be selected by specifying the option when preprocessing the source code for compilation. Last, the authors determine thermophysical properties such as surface tension, thermal conductivities, and viscosities in the model for the intracell exchanges of AFDM. Specific notations, routines, EOS data, plots, test results, and corrections to the code are available in the appendices.
Date:
January 1, 1994
Creator:
Henneges, G. & Kleinheins, S.
Object Type:
Report
System:
The UNT Digital Library
Air ingression calculations for selected plant transients using MELCOR
Two sets of MELCOR calculations have been completed studying the effects of air ingression on the consequences of various severe accident scenarios. One set of calculations analyzed a station blackout with surge line failure prior to vessel breach, starting from nominal operating conditions; the other set of calculations analyzed a station blackout occurring during shutdown (refueling) conditions. Both sets of analyses were for the Surry plant, a three-loop Westinghouse PWR. For both accident scenarios, a basecase calculation was done, and then repeated with air ingression from containment into the core region following core degradation and vessel failure. In addition to the two sets of analyses done for this program, a similar air-ingression sensitivity study was done as part of a low-power/shutdown PRA, with results summarized here; that PRA study also analyzed a station blackout occurring during shutdown (refueling) conditions, but for the Grand Gulf plant, a BWR/6 with Mark III containment. These studies help quantify the amount of air that would have to enter the core region to have a significant impact on the severe accident scenario, and demonstrate that one effect, of air ingression is substantial enhancement of ruthenium release. These calculations also show that, while the core clad …
Date:
January 1, 1994
Creator:
Kmetyk, L. N.
Object Type:
Report
System:
The UNT Digital Library
Air Pathway Analysis for Cleanup at the Chemical Plant Area of the Weldon Spring Site
The Weldon Spring site is a mixed waste site located in St. Charles County, Missouri. Cleanup of the site is in the planning and design stage, and various engineering activities were considered for remedial action, including excavating soils, dredging sludge, treating various contaminated media in temporary facilities, transporting and staging supplies and contaminated material, and placing waste in an engineered disposal cell. Both contaminated and uncontaminated emissions from these activities were evaluated to assess air quality impacts and potential health effects for workers and the general public during the cleanup period. A site-specific air quality modeling approach was developed to address several complex issues, such as a variety of emission sources, an array of source/receptor configurations, and complicated sequencing/scheduling. This approach can be readily adapted to reflect changes in the expected activities as engineering plans are finalized.
Date:
January 1, 1994
Creator:
Chang, Y. S.
Object Type:
Report
System:
The UNT Digital Library
AIRSOURC code aerosol model in radioactive waste tanks
An aerosol model was developed for a radioactive waste tank vapor space and ventilation system. The source of aerosol formation was modeled from gas bubble bursts at the liquid surface. The gases contained in these bubbles are formed by radiolytic breakdown of liquid and organic materials in the radioactive tank contents. The model accounts for the rate of radiolytic gas formation and the rate of tank liquids that are released as aerosols. The concentration of particles in the tank vapor are modeled as a function of the deposition rate of dry particles and the vapor removal rate by ventilation. The ventilation rate in tanks without an active ventilation system has a threshold level that is driven by atmospheric pressure variation. The model predictions are compared to measurements in several typical waste tank vapors of the Hanford Site waste storage tanks.
Date:
January 1, 1994
Creator:
Roblyer, S. P.
Object Type:
Article
System:
The UNT Digital Library
Alternatives evaluation for the decontamination and decommissioning of buildings 3506 and 3515 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program
this is an alternative evaluation document that records the evaluation process and justification for choosing the alternative recommended for the decontamination and decommissioning (D&D) of the 3506 and 3515 buildings at the Oak Ridge National Laboratory (ORNL). The alternatives for the D&D of the two buildings were: (1) no action (continued surveillance and maintenance), (2) decontamination for free release, (3) entombment in place, (4) partial dismantlement, and (5) complete dismantlement. Soil remediation is not included in any of the alternatives. The recommended alternative for the D&D of Building 3506 is partial dismantlement at an estimated cost of $936, 000 in escalated dollars. The cost estimate for complete dismantlement is $1,384,000. The recommended alternative for the D&D of Building 3515 is complete dismantlement at an estimated cost of $3,733,000 in escalated dollars. This alternative is recommended, because the soils below the foundation of the 3515 building are highly contaminated, and removing the foundation in the D&D project results in lower overall worker risk, costs, and improved post-D&D site conditions. A further recommendation is to revise these cost estimates after the conclusion of the ongoing characterization study. The results of the characterization of the two buildings is expected to change some of …
Date:
January 1, 1994
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Alu repeats as markers for forensic DNA analyses
The Human-Specific (HS) subfamily of Alu sequences is comprised of a group of 500 nearly identical members which are almost exclusively restricted to the human genome. Individual subfamily members share an average of 98.9% nucleotide identity with the HS subfamily consensus sequence, and have an average age of 2.8 million years. We have developed a Polymerase Chain Reaction (PCR) based assay using primers complementary to the 5 inch and 3 inch unique flanking DNA sequences from each HS Alu that allow the locus to be assayed for the presence or absence of the Alu repeat. The dimorphic HS Alu sequences probably inserted in the human genome after the radiation of modem humans (within the last 200,000-one million years) and represent a unique source of information for human population genetics and forensic DNA analyses. These sites can be developed into Dimorphic Alu Sequence Tagged Sites (DASTS) for the Human Genome Project. HS Alu family member insertions differ from other types of polymorphism (e.g. Variable Number of Tandem Repeat [VNTR] or Restriction Fragment Length Polymorphism [RFLP]) in that polymorphisms due to Alu insertions arise as a result of a unique event which has occurred only one time in the human population and …
Date:
January 1, 1994
Creator:
Batzer, M. A.; Alegria-Hartman, M. & Kass, D. H.
Object Type:
Article
System:
The UNT Digital Library
Analyses of postulated ALMR containment and steam generator building accidents using the CONTAIN-LMR code
The development of liquid metal reactor concepts with passive safety characteristics is in progress at the General Electric Company under contract to the US Department of Energy. To assess the performance of these systems under postulated severe accident conditions analyses of containment accidents relating to the breach of the primary coolant boundary of the Department of Energy Advanced Liquid Metal Reactor were completed by Westinghouse Hanford Company for the plant designer General Electric. A series of three accident cases were selected by General Electric for characterizing the containment responding to a hypothetical core disruptive accident. In addition, the Advanced Liquid Metal Reactor Steam Generator Building was also analyzed to demonstrate the acceptability of the Steam Generator Building sodium fire protection strategy related to a design-basis leak.
Date:
January 1, 1994
Creator:
Chiao, T.; Wood, S. A.; Shen, P. K.; Baker, R. B. & Gluekler, E. L.
Object Type:
Article
System:
The UNT Digital Library
Analysis/Control of in-Bed Tube Erosion Phenomena in the Fluidized Bed Combustion (FBC) System. Technical Progress Report No. 5
This technical report summarizes the research work performed and progress achieved during the period of October 1, 1993 to December 31, 1993. Measurement of particle-tube collision frequency was conducted by an electrostatic impact probe in the bench-scale FBC model. Two series of tests were conducted, in one test the probe traversed vertically along the bed axis. The other test conducted that the probe traversed from the center position to the quarter point of bed diagonal and the wall region. The specific weight loss at different tube circumferential was examined to understand the effect of superficial fluidizing velocity. The bottom section of the test tube was found to be more serious erosion than that of the top section. In order to study the effect of tube orientations on in-bed tube erosion, the sample tubes along with four different angles were used. The sample tubes were also placed horizontally and vertically at the center, and vertically near the wall to quantify the effect of the tube location.
Date:
January 1, 1994
Creator:
Lee, S. W.
Object Type:
Report
System:
The UNT Digital Library
Analysis of a High Velocity Oxygen-Fuel (HVOF) thermal spray torch. Part 1, Numerical formulation
The fluid and particle dynamics of a High Velocity Oxygen-Fuel (HVOF) torch are analyzed using computational fluid dynamic (CFD) techniques. The thermal spray device analyzed is similar to a Metco Diamond Jet torch with powder injection. The spray nozzle is axisymmetric with powder injection on the centerline, premixed fuel and oxygen fed from an annulus, and air cooling injected along the interior surface of the aircap. Choked flow conditions occur at the exit of the aircap and a supersonic, under-expanded jet develops externally. The CFD simulation assumes three injection streams (solid metal particles with argon as a carrier gas, premixed oxygen/fuel, and air) inside the aircap and solves the combusting two-phase flow until the external spray stream decays to sonic conditions. The numerical formulation solves the mass, momentum, and energy transfer for both the gas and particle phase and strongly couples each phase. The combustion process is modeled using approximate equilibrium chemistry with dissociation of the gas with a total of nine species. Melting and re-solidification of the metal panicles is modeled as a lumped-mass system. Turbulent flow is modeled by a two equation k-{epsilon} turbulence model, including compressibility effects on turbulent dissipation. A time iterative, implicit, finite volume numerical …
Date:
January 1, 1994
Creator:
Oberkampf, W. L. & Talpallikar, M.
Object Type:
Article
System:
The UNT Digital Library