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A Light to the Nations: Messages from Isaiah. The 76th Annual Bible Lectures
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Degree Department
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Month
Language
Magnetless magnetic fusion
The authors propose a concept of thermonuclear fusion reactor in which the plasma pressure is balanced by direct gas-wall interaction in a high-pressure vessel. The energy confinement is achieved by means of the self-contained toroidal magnetic configuration sustained by an external current drive or charged fusion products. This field structure causes the plasma pressure to decrease toward the inside of the discharge and thus it should be magnetohydrodynamically stable. The maximum size, temperature and density profiles of the reactor are estimated. An important feature of confinement physics is the thin layer of cold gas at the wall and the adjacent transitional region of dense arc-like plasma. The burning condition is determined by the balance between these nonmagnetized layers and the current-carrying plasma. They suggest several questions for future investigation, such as the thermal stability of the transition layer and the possibility of an effective heating and current drive behind the dense edge plasma. The main advantage of this scheme is the absence of strong external magnets and, consequently, potentially cheaper design and lower energy consumption.
Date:
February 1, 1994
Creator:
Beklemishev, A. D. & Tajima, T.
Object Type:
Report
System:
The UNT Digital Library
Magnetohydrodynamic simulation of solid-deuterium-initiated Z-pinch experiments
Solid-deuterium-initiated Z-pinch experiments are numerically simulated using a two-dimensional resistive magnetohydrodynamic model, which includes many important experimental details, such as ``cold-start`` initial conditions, thermal conduction, radiative energy loss, actual discharge current vs. time, and grids of sufficient size and resolution to allow realistic development of the plasma. The alternating-direction-implicit numerical technique used meets the substantial demands presented by such a computational task. Simulations of fiber-initiated experiments show that when the fiber becomes fully ionized rapidly developing m=0 instabilities, which originated in the coronal plasma generated from the ablating fiber, drive intense non-uniform heating and rapid expansion of the plasma column. The possibility that inclusion of additional physical effects would improve stability is explored. Finite-Larmor-radius-ordered Hall and diamagnetic pressure terms in the magnetic field evolution equation, corresponding energy equation terms, and separate ion and electron energy equations are included; these do not change the basic results. Model diagnostics, such as shadowgrams and interferograms, generated from simulation results, are in good agreement with experiment. Two alternative experimental approaches are explored: high-current magnetic implosion of hollow cylindrical deuterium shells, and ``plasma-on-wire`` (POW) implosion of low-density plasma onto a central deuterium fiber. By minimizing instability problems, these techniques may allow attainment of higher temperatures …
Date:
February 1, 1994
Creator:
Sheehey, P. T.
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library
Making contracting work better and cost less: Report of the Contract Reform Team
In June 1993, Secretary of Energy Hazel O`Leary formed a Contract Reform Team, chaired by Deputy Secretary Bill White, to evaluate the contracting practices of the Department of Energy and to formulate specific proposals for improving those practices. This report summarizes the results of the work of the Contract Reform Team. It recommends actions for implementation that will significantly improve the Department`s contracting practices and will enable the Department to help create a government that -- in the words of Vice President Gore -- {open_quotes}works better and costs less.{close_quotes} These actions and the deadlines for their implementation are listed. Among other things, they recommend replacing the Department`s standard Management and Operating Contract with a new Performance-Based Management Contract and strengthening the Department`s systems for selecting and managing contractors.
Date:
February 1, 1994
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Managing performance of DB2 Ad Hoc Reports
The DB2 financial reporting systems at Westinghouse Savannah River Company consists of 212 standardized reports that over 1034 users have accessed in 1993 to generate their reports. Each report has a range of selection criteria that the users can specify. Depending on the selection criteria, a report can access from a few rows to millions of rows of data. When this new DB2 system went into production in 1992, the CPU was at 100% utilization. From the beginning, ad hoc reports had a backlog of 4--5 days. Since DB2 was a new DBMS, most people blamed the poor report turn around times on DB2 as an inefficient DBMS and on a shortage of CPU cycles. Since we are unable to purchase a more powerful CPU, the only option left to us was to improve report turn around was system and application performance tuning. This document presents our efforts in these areas. Education of users in report submission was a starting point. And as to index tuning techniques that were applied, we created more friendly indexes, used clustering indexes, and used a reorganizing mechanism. A more efficient SQL was written which saved a lot of money.
Date:
February 1, 1994
Creator:
Chow, A.
Object Type:
Article
System:
The UNT Digital Library
Mass model for unstable nuclei
We present some essential features of a macroscopic-microscopic nuclear-structure model, with special emphasis on the results of a recent global calculation of nuclear masses. We discuss what should be some minimal requirements of a nuclear mass model and study how the macroscopic-microscopic method and other nuclear mass models fulfil such basic requirements. We study in particular the reliability of nuclear mass models in regions of nuclei that were not considered in the determination of the model parameters.
Date:
February 1, 1994
Creator:
Moeller, P. & Nix, J. R.
Object Type:
Article
System:
The UNT Digital Library
Materials research at selected Japanese laboratories. Based on a 1992 visit: Overview, summary of highlights, notes on laboratories and topics
I visited Japan from June 29 to August 1, 1992. The purpose of this visit was to assess the status of materials science research at selected governmental, university and industrial laboratories and to established acquaintances with Japanese researchers. The areas of research covered by these visits included ceramics, oxide superconductors, intermetallics alloys, superhard materials and diamond films, high-temperature materials and properties, mechanical properties, fracture, creep, fatigue, defects, materials for nuclear reactor applications and irradiation effects, high pressure synthesis, self-propagating high temperature synthesis, microanalysis, magnetic properties and magnetic facilities, and surface science.
Date:
February 1, 1994
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Materials Sciences programs, Fiscal year 1993
This report provides a compilation and index of the DOE Materials Sciences Division programs; the compilation is to assist administrators, managers, and scientists to help coordinate research. The report is divided into 7 sections: laboratory projects, contract research projects, small business innovation research, major user facilities, other user facilities, funding level distributions, and indexes.
Date:
February 1, 1994
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
MAXINE: An improved methodology for estimating maximum individual dose from chronic atmospheric radioactive releases
An EXCEL{reg_sign} spreadsheet has been developed that, when combined with the PC version of XOQDOQ, will generate estimates of maximum individual dose from routine atmospheric releases of radionuclides. The spreadsheet, MAXINE, utilizes a variety of atmospheric dispersion factors to calculate radiation dose as recommended by the US Nuclear Regulatory Commission in Regulatory Guide 1.109 [USNRC 1977a]. The methodology suggested herein includes use of both the MAXINE spreadsheet and the PC version of XOQDOQ.
Date:
February 1, 1994
Creator:
Hamby, D. M.
Object Type:
Report
System:
The UNT Digital Library
Measured thermal and fast neutron fluence rates, ATR Cycle 102-A, 11/28/93 thru 1/16/94
This report contains the thermal (2,200 m/s) and fast (E > 1MeV) neutron fluence rate data for ATR Cycle 102-A which were measured by the Radiation Measurements Laboratory (RML) as requested by the Power Reactor Programs (ATR Experiments) Radiation Measurements Work Order. This report contains fluence rate values corresponding to the particular elevations (relative to the 80 ft. core elevation) where the measurements were taken. The data in this report consists of (1) a table of the ATR power history and distribution, (2) a hard copy listing of all thermal and fast neutron fluence rates, (3) plots of both the thermal and fast neutron fluence rates, and (4) a magnetic record (3.5 inch diskette) containing a listing of only the fast neutron fluence rates, their assigned elevations and proper header identification of all monitor positions contained herein. The fluence rates reported are for the average power levels given in the table of power history and distribution. All ``H`` holder monitoring wires for this cycle are 54 inches long. All ``SR`` holder monitor wires for this cycle are 55 inches long. This length allows measurement of the full core region and makes the first count elevation 24.73 inches above core midplane. …
Date:
February 1, 1994
Creator:
Murray, R. K. & Rogers, J. W.
Object Type:
Report
System:
The UNT Digital Library
Measurement of ICF fuel ion temperature on Nova
A new diagnostic for measuring the average fuel ion temperature in inertial confinement fusion (ICF) targets at the time of peak burn has been constructed by Los Alamos and installed on the Nova Laser System at Lawrence Livermore National Laboratory. This ion-temperature diagnostic measures the time-of-flight of fusion neutrons and determines the thermonuclear-reaction-weighted ion temperature through the time-of-arrival distribution. Preliminary experiments have been designed and performed to test the diagnostic. These tests measured the ion temperature of targets designed to have varying temperatures and yields. Additionally, an experiment has been designed to examine the cause of the increase in yield degradation (compared to clean 1-D calculations) as the capsule convergence is increased. Understanding the cause of yield degradation in high convergence implosions is necessary to increase the confidence of the target performance for the next generation National Ignition Facility planned by the US ICF Program.
Date:
February 1, 1994
Creator:
Harris, D. B. & Chrien, R. E.
Object Type:
Article
System:
The UNT Digital Library
A measurement of the e{sup +}e{sup {minus}} decay width of the Z{sup 0}
This thesis presents a measurement of the partial decay width of the Z{sup 0} to e{sup +}e{sup {minus}} using data recorded by the SLD at the SLAC Linear Collider during the 1992 run. Based on 354 nb{sup {minus}1} of data, the decay width, {Gamma}{sub ee} is measured to be 82.4 {+-} 3.6/3.7 {+-} 0.8 MeV where the first error is statistical and the second is systematic. By combining this measurement of {Gamma}{sub ee} with the SLD measurement of A{sub LR}, the magnitude of the effective vector and axial-vector coupling constants of the electron, {anti g}{sub v}{sup e} and {anti g}{sub a}{sup e}, are determined to be 0.024 {+-} 0.011 and 0.498 {+-} 0.011 respectively.
Date:
February 1, 1994
Creator:
Yamartino, J. M.
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library
[Meg Hentges and Jude O'nym in Studio]
Photograph of Meg Hentges with her arm around Jude O'nym's shoulders in a studio. Hentges is wearing a white jacket and black glasses and looking at the camera and O'nym is wearing a white shirt and overalls and looking over at Hentges.
Date:
February 1994
Creator:
Davis, Lisa
Object Type:
Photograph
System:
The Portal to Texas History
[Meg Hentges, Darcee Douglas, and Musician in a Studio]
Photograph of Meg Hentges, Darcee Douglas, and another musician in a studio. Douglas is standing on the right and playing the guitar, Hentges is standing in the middle and looking down, and a third musician is sitting on a cushion on the left and playing the guitar.
Date:
February 1994
Creator:
Davis, Lisa
Object Type:
Photograph
System:
The Portal to Texas History
[Meg Hentges in Studio With Headphones and Microphone]
Photograph of Meg Hentges during a studio session; she has headphones on and and is standing next to a studio microphone.
Date:
February 1994
Creator:
Davis, Lisa
Object Type:
Photograph
System:
The Portal to Texas History
Megapixel Imaging Camera for Expanded H{sup {minus}} Beam Measurements
A charge coupled device (CCD) imaging camera system has been developed as part of the Ground Test Accelerator project at the Los Alamos National Laboratory to measure the properties of a large diameter, neutral particle beam. The camera is designed to operate in the accelerator vacuum system for extended periods of time. It would normally be cooled to reduce dark current. The CCD contains 1024 {times} 1024 pixels with pixel size of 19 {times} 19 {mu}m{sup 2} and with four phase parallel clocking and two phase serial clocking. The serial clock rate is 2.5{times}10{sup 5} pixels per second. Clock sequence and timing are controlled by an external logic-word generator. The DC bias voltages are likewise located externally. The camera contains circuitry to generate the analog clocks for the CCD and also contains the output video signal amplifier. Reset switching noise is removed by an external signal processor that employs delay elements to provide noise suppression by the method of double-correlated sampling. The video signal is digitized to 12 bits in an analog to digital converter (ADC) module controlled by a central processor module. Both modules are located in a VME-type computer crate that communicates via ethernet with a separate workstation …
Date:
February 1, 1994
Creator:
Simmons, J. E.; Lillberg, J. W.; McKee, R. J.; Slice, R. W.; Torrez, J. H.; McCurnin, T. W. et al.
Object Type:
Report
System:
The UNT Digital Library
MELCOR 1.8.2 assessment: Surry PWR TMLB` (with a DCH study)
MELCOR is a fully integrated, engineering-level computer code, being developed at Sandia National Laboratories for the USNRC. This code models the entire spectrum of severe accident phenomena in a unified framework for both BWRs and PWRs. As part of an ongoing assessment program, the MELCOR computer code has been used to analyze a station blackout transient in Surry, a three-loop Westinghouse PWR. Basecase results obtained with MELCOR 1.8.2 are presented, and compared to earlier results for the same transient calculated using MELCOR 1.8.1. The effects of new models added in MELCOR 1.8.2 (in particular, hydrodynamic interfacial momentum exchange, core debris radial relocation and core material eutectics, CORSOR-Booth fission product release, high-pressure melt ejection and direct containment heating) are investigated individually in sensitivity studies. The progress in reducing numeric effects in MELCOR 1.8.2, compared to MELCOR 1.8.1, is evaluated in both machine-dependency and time-step studies; some remaining sources of numeric dependencies (valve cycling, material relocation and hydrogen burn) are identified.
Date:
February 1, 1994
Creator:
Kmetyk, L. N.; Cole, R. K., Jr.; Smith, R. C.; Summers, R. M. & Thompson, S. L.
Object Type:
Report
System:
The UNT Digital Library
Mercury audit at Rocky Mountain Arsenal
This report presents the results of an environmental compliance audit to identify potential mercury-containing equipment in 261 building and 197 tanks at the Rocky Mountain Arsenal (RMA). The RMA, located near Denver, Colorado, is undergoing clean up and decommissioning by the Department of the Army. Part of the decommissioning procedure is to ensure that all hazardous wastes are properly identified and disposed of. The purpose of the audit was to identify any mercury spills and mercury-containing instrumentation. The audit were conducted from April 7, 1992, through July 16, 1992, by a two-person team. The team interviewed personnel with knowledge of past uses of the buildings and tanks. Information concerning past mercury spills and the locations and types of instrumentation that contain mercury proved to be invaluable for an accurate survey of the arsenal. The team used a Jerome{reg_sign} 431-X{trademark} Mercury Vapor Analyzer to detect spills and confirm locations of mercury vapor. Twelve detections were recorded during the audit and varied from visible mercury spills to slightly elevated readings in the corners of rooms with past spills. The audit also identified instrumentation that contained mercury. All data have been incorporated into a computerized data base that is compatible with the RMA …
Date:
February 1, 1994
Creator:
Smith, S. M.; Jensen, M. K. & Anderson, G. M.
Object Type:
Report
System:
The UNT Digital Library
The Meteorological Monitoring program at a former nuclear weapons plant
The purpose of the Meteorological Monitoring program at Rocky Flats Plant (RFP) is to provide meteorological information for use in assessing the transport, and diffusion, and deposition of effluent actually or potentially released into the atmosphere by plant operations. Achievement of this objective aids in protecting health and safety of the public, employees, and environment, and directly supports Emergency Response programs at RFP. Meteorological information supports the design of environmental monitoring networks for impact assessments, environmental surveillance activities, remediation activities, and emergency responses. As the mission of the plant changes from production of nuclear weapons parts to environmental cleanup and economic development, smaller releases resulting from remediation activities become more likely. These possible releases could result from airborne fugitive dust, evaporation from collection ponds, or grass fires.
Date:
February 1, 1994
Creator:
Maxwell, D. R. & Bowen, B. M.
Object Type:
Article
System:
The UNT Digital Library
Method for removal of heavy metal from molten salt in IFR fuel pyroprocessing
This report details the pyrometallurgical process for recycling spent metal fuels from the Integral Fast Reactor (IFR) which involves electrorefining spent fuel in a molten salt electrolyte (LiCl-KCI-U/PuCl{sub 3}) at 500{degree}C. The total heavy metal chloride concentration in the salt will be about 2 mol %. At some point, the concentrations of alkali, alkaline earth, and rare earth fission products in the salt must be reduced to lower the amount of heat generated in the electrorefiner. The heavy metal concentration in the salt must be reduced before removing the fission products from the salt. The operation uses a lithium-cadmium alloy anode that is solid at 500{degree}C, a solid mandrel cathode with a ceramic catch crucible below to collect heavy metal that falls off it, and a liquid cadmium cathode. The design criteria that had to be met by this equipment included the following: (1) control of the reduction rate by lithium, (2) good separation between heavy metal and rare earths, and (3) the capability to collect heavy metal and rare earths over a wide range of salt compositions. In tests conducted in an engineering-scale electrorefiner (10 kg uranium per cathode), good separation was achieved while removing uranium and rare earths …
Date:
February 1, 1994
Creator:
Gay, E. C.; Miller, W. E. & Laidler, J. J.
Object Type:
Article
System:
The UNT Digital Library
Methodology and computational framework used for the US Department of Energy Environmental Restoration and Waste Management Programmatic Environmental Impact Statement accident analysis
A methodology, computational framework, and integrated PC-based database have been developed to assess the risks of facility accidents in support of the US Department of Energy (DOE) Environmental Restoration and Waste Management Programmatic Environmental Impact Statement. The methodology includes the following interrelated elements: (1) screening of storage and treatment processes and related waste inventories to determine risk-dominant facilities across the DOE complex, (2) development and frequency estimation of the risk-dominant sequences of accidents, and (3) determination of the evolution of and final compositions of radiological or chemically hazardous source terms predicted to be released as a function of the storage inventory or treatment process throughput. The computational framework automates these elements to provide source term input for the second part of the analysis which includes (1) development or integration of existing site-specific demographics and meteorological data and calculation of attendant unit-risk factors and (2) assessment of the radiological or toxicological consequences of accident releases to the general public and to the occupational work force.
Date:
February 1, 1994
Creator:
Mueller, C.; Roglans-Ribas, J.; Folga, S.; Huttenga, A.; Jackson, R.; TenBrook, W. et al.
Object Type:
Article
System:
The UNT Digital Library
Methodology for integrated evaluation of alternative siting and treatment, storage, and disposal strategies for U.S. Department of Energy waste management
A computational model named WASTE-MGMT has been developed by Argonne National Laboratory in support of the U.S. Department of Energy (DOE) Environmental Restoration and Waste Management (EM) Programmatic Environmental Impact Statement (PEIS) to assist in the analysis of alternative approaches to the management of existing and future radioactive wastes at DOE facilities. Input to the model includes waste inventory and characterization data at each DOE site; unit operations data for the facilities used for treatment, storage and disposal (TSD) of the wastes; and information about the alternative approaches for the TSD of the wastes and for the siting of such TSD facilities. The quantities calculated by the model include the air emissions of radionuclides and hazardous chemicals during operation of the TSD facilities, the quantities and characteristics of the wastes processes annually at these facilities, and the quantities and characteristics of the waste shipped among sites. These quantities are then used as input to calculate the cost and the environmental and socioeconomic impacts resulting from the TSD of the DOE wastes under various alternative management approaches considered in the EM PEIS.
Date:
February 1, 1994
Creator:
Avci, H.; Habegger, L. & Kotek, T.
Object Type:
Article
System:
The UNT Digital Library
Methyl chloride via oxyhydrochlorination of methane. Quarterly technical progress report No. 9, October 1993--December 1993
The purpose of this contract is to develop a process for converting light alkane gases to methyl chloride via oxyhydrochlorination using highly selective, stable catalysts in fixed-bed reactors designed to remove the large amount of heat generated, so as to control the reaction temperature. Further, the objective is to obtain the engineering data base necessary for developing a commercially feasible process and to evaluate the economics of the process. The key technical progress this quarter was the great deal of progress in equipment design, instrument selection and data sheet preparation for the PDU. This work is outlined under the Task 2.0 and 3.0 sections below. Catalyst definition this quarter provided limited progress due to the attempt to start up a new screening reactor than ran at higher pressures. The use of high pressure without the availability of a HCl removal unit operation resulted in many experimental problems. This will be solved by the use of the separation unit operation lab equipment as a catalyst screening reactor in the future. Work continued on the development of the separation system. Results showed that at a given pressure and L/G , as the amount of methyl chloride in the feed gas increases, the …
Date:
February 1, 1994
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
MHD stability regimes for steady state and pulsed reactors
A tokamak reactor will operate at the maximum value of {beta}{equivalent_to}2{mu}{sub 0} < p >/B{sup 2} that is compatible with MHD stability. This value depends upon the plasma current and pressure profiles, the plasma shape and aspect ratio, and the location of nearby conducting structures. In addition, a steady state reactor will minimize its external current drive requirements and thus achieve its maximum economic benefit with a bootstrap fraction near one, I{sub bs}/I{sub p} {approximately} 1, which constrains the product of the inverse aspect ratio and the plasma poloidal beta to be near unity, {epsilon} {beta}{sub p} {approximately} 1. An inductively driven pulsed reactor has different constraints set by the steady-state Ohm`s law which relates the plasma temperature and density profiles to the parallel current density. We present the results obtained during the ARIES I, II/IV, and III and the PULSAR reactor studies where these quantities were optimized subject to different design philosophies. The ARIES-II/IV and ARIES-III designs are both in the second stability regime, but differ in requirements on the form of the profiles at the plasma edge, and in the location of the conducting wall. The relation between these, as well as new attractive MHD regimes not utilized …
Date:
February 1, 1994
Creator:
Jardin, S. C.; Kessel, C. E. & Pomphrey, N.
Object Type:
Article
System:
The UNT Digital Library
MHTGR nuclear physics benchmarks
None
Date:
February 1, 1994
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library