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ARAC dispersion modeling of the August 1998 Tracy, California tire fire

Description: At about 4:30 pm PDT on Friday, August 7, 1998 a fire ignited the large tire disposal pit of Royster Tire Co. on Macarthur Drive about 5 km (3 miles) south of downtown Tracy, California. While providing on-scene mutual aid late Friday night, the LLNL Fire Department called and requested that the Atmospheric Release Advisory Capability (ARAC) make a plume forecast for Saturday. The response team in the field was interested in the forecasted location as well as an estimate of potential health effects on the following day. Not having any previous experience with tire fire source terms, ARAC assessors used a constant unit source rate (1 g/s) of particulate and produced plots showing only the location of the ground-level normalized time-integrated air concentrations from the smoke plume. Very early Saturday morning the assessors faxed plots of ground-level smoke air concentrations forecasted for Saturday from 6 am through 6 pm PDT to the Tracy Fire Emergency Operations Center. (As a part of standard procedure, before delivering the plots, the assessors notified ARAC's DOE sponsor.) Fortunately due to the intense heat from the fire, the dense black smoke immediately lofted into the air preventing high ground-level concentrations close to the tire dump. Later on Saturday morning ARAC forecasted a second set of plume integrated air concentrations for Sunday. By Monday the intensity of the fire lessened, and ARAC's support was no longer requested. Following ARAC's response, we made a third calculation on a large scale of the continuous smoke dispersion for 3 days after the fire. A newspaper photograph showed the plume initially rising toward the northeast and the upper part of the smoke cloud turning counterclockwise toward the north. Winds from ARAC's mesoscale prognostic model reproduced this plume structure, while data from the Friday afternoon sounding from Oakland did not. ...
Date: August 28, 1998
Creator: Aluzzi, F J; Baskett, R L; Bowen, B M; Foster, C S; Pace, J C; Pobanz, B et al.

Argonne National Laboratory-East site environmental report for calendar year 1997.

Description: This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL-E) for 1997. To evaluate the effects of ANL-E operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL-E site were analyzed and compared with applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL-E effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (i.e., natural, fallout, ANL-E, and other) and are compared with applicable environmental quality standards. A US Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, was used in preparing this report. The status of ANL-E environmental protection activities with respect to the various laws and regulations that govern waste handling and disposal is discussed, along with the progress of environmental corrective actions and restoration projects.
Date: August 28, 1998
Creator: Golchert, N.W. & Kolzow, R.G.

Asymmetric B-factory note

Description: Three main issues giving purpose to our visit to CERN, ESRF and DESY were to: assess the current thinking at CERN on whether Eta, the gas desorption coefficient, would continue to decrease with continued with continued beam cleaning, determine if the time between NEG reconditioning could be expanded, and acquire a knowledge of the basic fabrication processes and techniques for producing beam vacuum chambers of copper.
Date: August 28, 1990
Creator: Calderon, M.

Contract administration involving the remedial investigation and feasibility study at the Feed Materials Production Center

Description: Advanced Sciences, Incorporated (ASI), has been performing a Remedial Investigation and Feasibility Study (RI/FS) at the Feed Materials Production Center (Fernald Facility) at Fernald, Ohio, under an 8 (a) contract with the US Small Business Administration (SBA). The Fernald Facility is a Government-owned facility operated by Westinghouse Materials Company of Ohio (WMCO) under a management and operating contract. The objective of this audit was to evaluate the award and administration of the ASI contract.
Date: August 28, 1991

D0 Silicon Upgrade: Upgrade Piping Loads on Cleanroom Roof

Description: The proposed piping layout for the DO upgrade will run along the south wall of DAB. The cryogenic service pipe runs above the upper and lower cleanroom roofs and will need to be supported by the roofs beams. Calculations were done to determine the stresses in the I-beams created by the existing and additional loads due to the upgrade. Refer to drawing no. 3823.115-ME-317283 for drawings of the piping layout. Figure 1 shows the 'plan view' portion of this drawing. The weight of the individual lines were calculated in figure 2 assuming a pipe density of O.28 lbm/in{sup 3} for stainless steel (0.12% C) and a fluid density (assuming LN2 at 1 atm) of 0.03 lbm/in{sup 3}. The weights of the corrugated steel flooring, assembly hall feed cans, support beams, and roof hatch were also included in the analysis. These loads are calculated on pgs. 5-6. A floor load of 50 lbf/ft{sup 2} was also added in order to maintain the existing floor load limit in addition to the added piping loads. Measurements of the dimensions of the I-beams determined that the nominal sizes of the beams were W8 x 21 for the lower roof and W14 x 26 for the upper roof. Pipe lengths were determined from the drawing for each of the lines on pgs. 1-2 of the calculations (refer to all piping by line numbers according to figure 2). A total weight was calculated for lines 3-9 along the south wall and lines 1-2 running along the north wall of the lower cleanroom roof. To simplify the calculations these weights were assumed to be evenly distributed on the 5 I-beam supports of the lower cleanroom roof 2.5 feet in from the south wall. The stress analysis was done using FrameMac, a 2-D finite element program for the ...
Date: August 28, 1995
Creator: Sakla, Steve

Disposal of NORM-contaminated oil field wastes in Salt Caverns.

Description: In 1995, the U.S. Department of Energy (DOE), Office of Fossil Energy, asked Argonne National Laboratory (Argonne) to conduct a preliminary technical and legal evaluation of disposing of nonhazardous oil field waste (NOW) into salt caverns. That study concluded that disposal of NOW into salt caverns is feasible and legal. If caverns are sited and designed well, operated carefully, closed properly, and monitored routinely, they can be a suitable means of disposing of NOW (Veil et al. 1996). Considering these findings and the increased U.S. interest in using salt caverns for NOW disposal, the Office of Fossil Energy asked Argonne to conduct further research on the cost of cavern disposal compared with the cost of more traditional NOW disposal methods and on preliminary identification and investigation of the risks associated with such disposal. The cost study (Veil 1997) found that disposal costs at the four permitted disposal caverns in the United States were comparable to or lower than the costs of other disposal facilities in the same geographic area. The risk study (Tomasko et al. 1997) estimated that both cancer and noncancer human health risks from drinking water that had been contaminated by releases of cavern contents were significantly lower than the accepted risk thresholds. Since 1992, DOE has funded Argonne to conduct a series of studies evaluating issues related to management and disposal of oil field wastes contaminated with naturally occurring radioactive material (NORM). Included among these studies were radiological dose assessments of several different NORM disposal options (Smith et al. 1996). In 1997, DOE asked Argonne to conduct additional analyses on waste disposal in salt caverns, except that this time the wastes to be evaluated would be those types of oil field wastes that are contaminated by NORM. This report describes these analyses. Throughout the remainder of this ...
Date: August 28, 1998
Creator: Veil, J. A.; Smith, K. P.; Tomasko, D.; Elcock, D.; Blunt, D. & Williams, G. P.

(Efficient identification and analysis of low and medium frequency repeats)

Description: The effective starting date of this grant was May 15. In the first three months of this project we focused primarily on organizational and technical aspects of our research which included: organization of the database of repeats in primates; preparation of software for rapid and sensitive search of novel repetitive elements in GenBank; purchase and installation of the Sun workstation; and research on the mammal-specific MAR1 family of repetitive elements (to be communicated in October).
Date: August 28, 1991
Creator: Jurka, J.

[Efficient identification and analysis of low and medium frequency repeats]. Progress report

Description: The effective starting date of this grant was May 15. In the first three months of this project we focused primarily on organizational and technical aspects of our research which included: organization of the database of repeats in primates; preparation of software for rapid and sensitive search of novel repetitive elements in GenBank; purchase and installation of the Sun workstation; and research on the mammal-specific MAR1 family of repetitive elements (to be communicated in October).
Date: August 28, 1991
Creator: Jurka, J.

Electron beam bunch length characterizations using incoherent and coherent radiation on the APS SASE FEL project.

Description: The Advanced Photon Source (APS) injector linac has been reconfigured with a low-emittance rf thermionic gun and a photocathode (PC) rf gun to support self-amplified spontaneous emission (SASE) free-electron laser (FEL) experiments. One of the most critical parameters for optimizing SASE performance (gain length) is the electron beam peak current, which requires a charge measurement and a bunch length measurement capability. We report here initial measurements of the latter using both incoherent optical transition radiation (OTR) and coherent transition radiation (CTR), A visible light Hamarnatsu C5680 synchroscan streak camera was used to measure the thermionic rf gun beam's bunch length ({sigma} {approximately}2 to 3ps) via OTR generated by the beam at 220 MeV and 200 mA macropulse average current. In addition, a CTR monitor (Michelson Interferometer) based on a Golay cell as the far infrared (FIR) detector has been installed at the 40-MeV station in the beamline. Initial observation s of CTR signal strength variation with gun a-magnet current and interferograms have been obtained. Progress in characterizing the beam at these locations and a comparison to other bunch length determinations will be presented.
Date: August 28, 1999
Creator: Berg, W. J.; Happek, U.; Lewellen, J. W.; Lumpkin, A. H.; Sereno, N. S. & Yang, B. X.

Engineering development of advanced physical fine coal cleaning for premium fuel applications

Description: The primary goal of this project is the engineering development of two advanced physical fine coal cleaning processes, column flotation and selective agglomeration, for premium fuel applications. The project scope included laboratory research and bench-scale testing on six coals to optimize these processes, followed by the design, construction and operation of 2 t/hr process development unit (PDU). This report represents the findings of the PDU Advanced Column Flotation Testing and Evaluation phase of the program and includes a discussion of the design and construction of the PDU. Three compliance steam coals, Taggart, Indiana VII and Hiawatha, were processed in the PDU to determine performance and design parameters for commercial production of premium fuel by advanced flotation. Consistent, reliable performance of the PDU was demonstrated by 72-hr production runs on each of the test coals. Its capacity generally was limited by the dewatering capacity of the clean coal filters during the production runs rather than by the flotation capacity of the Microcel column. The residual concentrations of As, Pb, and Cl were reduced by at least 25% on a heating value basis from their concentrations in the test coals. The reduction in the concentrations of Be, Cd, Cr, Co, Mn, Hg, Ni and Se varied from coal to coal but the concentrations of most were greatly reduced from the concentrations in the ROM parent coals. The ash fusion temperatures of the Taggart and Indiana VII coals, and to a much lesser extent the Hiawatha coal, were decreased by the cleaning.
Date: August 28, 1997
Creator: Shields, G.L.; Smit, F.J. & Jha, M.C.

Enhanced adhesion buffer layer for deep x-ray lithography using hard x-rays.

Description: The first step in the fabrication of microstructure using deep x-ray lithography (DXRL) is the irradiation of a x-ray sensitive resist like polymethylmethacrylate (PMMA) by hard x-rays. At the Advanced Photon Source, a dedicated beamline allows the proper exposure of very thick (several mm) resists. To fabricate electroformed metal microstructure with heights of several mm, a PMMA sheet is glued onto a metallic plating base. An important requirement is that the PMMA layer must adhere well to the plating base. The adhesion is greatly reduced by the penetration of even a small fraction of hard x-rays through the mask absorber into the substrate. In this work we will show a novel technique to improve the adhesion of PMMA onto high-Z substrates for DXRL. Results of the improved adhesion are shown for different exposure/substrate conditions.
Date: August 28, 1998
Creator: De Carlo, F.

Environmental compliance program FY 1999 multi-year work plan, WBS 1.8.2.3

Description: The Environmental Compliance Program is developing and implementing a PHMC-wide chemical management system with the goal being to: (1) manage and control chemicals from procurement through use and final disposition; (2) develop and maintain procedures for identifying and evaluating hazards and environmental impacts present in facilities, and the hazard classification of the facilities. The US Department of Energy (DOE) may promulgate the final rule, 1 0 CFR 834, Radiation Protection of the Public and the Environment in FY 1999. This rule establishes controls for the release of radioactive material and limits for the amount of radiation exposure to the public and the environment. It will be applicable to activities of DOE contractors at the Hanford site. This rule is expected to replace the bulk of DOE Orders 5400.5, Radiation Protection of the Public and the Environment and 5400. 1, General Environmental Protection Program. In doing so, these Orders will be backed by the Price-Anderson enforcement procedures and carry penalties for non-compliance.
Date: August 28, 1998
Creator: Giese, K. A.

Exact calculations of phase and membrane equilibria for complex fluids by Monte Carlo simulation

Description: The general objective of this project is the investigation of phase equilibria for complex fluids using a novel methodology, Monte Carlo simulation in the Gibbs ensemble. The methodology enables the direct determination of the properties of two coexisting fluid phases (e.g. a liquid at equilibrium with its vapor) from a single computer experiment, and is applicable to multicomponent systems with arbitrary equilibrium constraints imposed. The specific goals of this work are to adapt the Gibbs technique to (a) highly asymmetric mixtures with large differences in size and potential energies of interaction (b) chain molecules and (c) ionic systems. Significant progress has been made in all three areas. In this paper, we will briefly describe the progress made in each area, using the same numbering scheme for the tasks as in the original proposal.
Date: August 28, 1990
Creator: Panagiotopoulos, A.Z.

Fire in a contaminated area

Description: This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: Fire in Contaminated Area. The calculations needed to quantify the risk associated with this accident scenario are included within.
Date: August 28, 1996
Creator: Ryan, G. W.

First Results for a Superconducting Imaging-Surface Sensor Array for Magnetocardiography

Description: The authors have completed fabrication and preliminary testing of a 12-channel SQUID array using the superconducting image-surface gradiometer concept. Sensor response to point dipole magnetic sources, and uniform fields used to simulate ambient magnetic fields followed predicted values to high precision. Edge effects were not observed for sources, within 5cm of the center of the imaging surface independent of whether the source is close or far from the surface. The superconducting imaging-surface also reduced uniform ambient fields at the SQUID sensors by approximately a factor of ten. Finally, a high degree of symmetry was observed between sides of the imaging surface for uniform fields. This symmetry, together with the very small sensitivity of sensors on the back side of the imaging surface to sources close to the front side provides an excellent circumstance for implementing either digital or analog background rejection. Their goal is to implement a higher density array with the superconducting imaging surface, together with background rejection, and utilize this system for MCG and other biomagnetic studies.
Date: August 28, 1998
Creator: Kraus, R.H. Jr.; Flynn, E.R.; Espy, M.A.; Matlachov, A.; Overton, W.; Wood, C.C. et al.

Formation and sustainment of a very low aspect ratio tokamak using coaxial helicity injection. Final report, June 1, 1995--May 31, 1997

Description: During the reporting period of this HIT grant (1 June 1995--31 May 1997) we`ve conducted further stability analysis, used the TIP diagnostic to measure plasma fields in HIT, and developed a single-parameter helicity injector model. HIT has undergone a significant upgrade to the HIT-II configuration which is described here. Parts for HIT-II have been designed, ordered, and received under this grant and are being assembled under the subsequent grant.
Date: August 28, 1997
Creator: Jarboe, T.R. & Nelson, B.A.

IMPACTT5A model : enhancements and modifications since December 1994 - with special reference to the effect of tripled-fuel-economy vehicles on fuel-cycle energy and emissions.

Description: Version 5A of the Integrated Market Penetration and Anticipated Cost of Transportation Technologies (IMPACTT5A) model is a spreadsheet-based set of algorithms that calculates the effects of advanced-technology vehicles on baseline fuel use and emissions. Outputs of this Argonne National Laboratory-developed model include estimates of (1) energy use and emissions attributable to conventional-technology vehicles under a baseline scenario and (2) energy use and emissions attributable to advanced- and conventional-technology vehicles under an alternative market-penetration scenario. Enhancements to IMPACIT made after its initial documentation in December 1994 have enabled it to deal with a wide range of fuel and propulsion system technologies included in Argonne's GREET model in a somewhat modified three-phased approach. Vehicle stocks are still projected in the largely unchanged STOCK module. Vehicle-miles traveled, fuel use, and oil displacement by advanced-technology vehicles are projected in an updated USAGE module. Now, both modules can incorporate vehicle efficiency and fuel share profiles consistent with those of the Partnership for a New Generation of Vehicles. Finally, fuel-cycle emissions of carbon monoxide, volatile organic compounds, nitrogen oxides, toxics, and greenhouse gases are computed in the EMISSIONS module via an interface with the GREET model that was developed specifically to perform such calculations. Because of this interface, results are now more broadly informative than were results from earlier versions of IMPACTT.
Date: August 28, 1999
Creator: Mintz, M. M. & Saricks, C. L.

K Basin sludge dissolution engineering study

Description: The purpose of this engineering study is to investigate the available technology related to dissolution of the K Basin sludge in nitric acid. The conclusion of this study along with laboratory and hot cell tests with actual sludge samples will provide the basis for beginning conceptual design of the sludge dissolver. The K Basin sludge contains uranium oxides, fragments of metallic U, and some U hydride as well as ferric oxyhydroxide, aluminum oxides and hydroxides, windblown sand that infiltrated the basin enclosure, ion exchange resin, and miscellaneous materials. The decision has been made to dispose of this sludge separate from the fuel elements stored in the basins. The sludge will be conditioned so that it meets Tank Waste Remediation System waste acceptance criteria and can be sent to one of the underground storage tanks. Sludge conditioning will be done by dissolving the fuel constituents in nitric acid, separating the insoluble material, adding neutron absorbers for criticality safety, and then reacting the solution with caustic to co-precipitate the uranium and plutonium. There will be five distinct feed streams to the sludge conditioning process two from the K East (KE) Basin and three from the K West (KW) Basin. The composition of the floor and pit sludges which contain more iron oxides and sand than uranium is much different than the canister sludges which are composed of mostly uranium oxides. The sludge conditioning equipment will be designed to process all of the sludge streams, but some of the operating parameters will be adjusted as necessary to handle the different sludge stream compositions. The volume of chemical additions and the amount of undissolved solids will be much different for floor and pit sludge than for canister sludge. Dissolution of uranium metal and uranium dioxide has been studied quite thoroughly and much information is ...
Date: August 28, 1998
Creator: Westra, A. G.

K Basin sludge treatment process description

Description: The K East (KE) and K West (KW) fuel storage basins at the 100 K Area of the Hanford Site contain sludge on the floor, in pits, and inside fuel storage canisters. The major sources of the sludge are corrosion of the fuel elements and steel structures in the basin, sand intrusion from outside the buildings, and degradation of the structural concrete that forms the basins. The decision has been made to dispose of this sludge separate from the fuel elements stored in the basins. The sludge will be treated so that it meets Tank Waste Remediation System (TWRS) acceptance criteria and can be sent to one of the double-shell waste tanks. The US Department of Energy, Richland Operations Office accepted a recommendation by Fluor Daniel Hanford, Inc., to chemically treat the sludge. Sludge treatment will be done by dissolving the fuel constituents in nitric acid, separating the insoluble material, adding neutron absorbers for criticality safety, and reacting the solution with caustic to co-precipitate the uranium and plutonium. A truck will transport the resulting slurry to an underground storage tank (most likely tank 241-AW-105). The undissolved solids will be treated to reduce the transuranic (TRU) and content, stabilized in grout, and transferred to the Environmental Restoration Disposal Facility (ERDF) for disposal. This document describes a process for dissolving the sludge to produce waste streams that meet the TWRS acceptance criteria for disposal to an underground waste tank and the ERDF acceptance criteria for disposal of solid waste. The process described is based on a series of engineering studies and laboratory tests outlined in the testing strategy document (Flament 1998).
Date: August 28, 1998
Creator: Westra, A. G.