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Cluster expansion of fcc Pd-V intermetallics
A cluster expansion is used to compute fcc ground states from first principles for the Pd-V system. Intermetallic structures are not assumed but derived rigorously by minimizing the configurational energy subject to linear constraints. A large number of concentration-independent interactions are calculated by the method of direct configurational averaging. Agreement with the fcc-based portion of the experimentally-determined Pd-V phase diagram is quite satisfactory. 25 refs., 2 figs.
Date:
June 1, 1991
Creator:
de Fontaine, D.; Wolverton, C.; Ceder, G. (Lawrence Berkeley Lab., CA (United States)) & Dreysse, H. (Nancy-1 Univ., 54 (France). Lab. de Physique du Solide)
Object Type:
Article
System:
The UNT Digital Library
Design of the Digital Sky Survey DA and online system---A case history in the use of computer aided tools for data acquisition system design
As part of its expanding Astrophysics program, Fermilab is participating in the Digital Sky Survey (DSS). Fermilab is part of a collaboration involving University of Chicago, Princeton University, and the Institute of Advanced Studies (at Princeton). DSS main results will be a photometric imaging survey and a redshift survey of galaxies and color-selected quasars over {pi} steradians of the Northern Galactic Cap. This paper focuses on our use of Computer Aided Software Engineering (CASE) in specifying the data system for DSS. Extensions to standard'' methodologies were necessary to compensate for tool shortcomings and to improve communication amongst the collaboration members. One such important extension was the incorporation of CASE information into the specification document. 7 refs.
Date:
June 1, 1991
Creator:
Petravick, D.; Berman, E.; Nicinski, T.; Rechenmacher, R.; Oleynik, G.; Pordes, R. et al.
Object Type:
Article
System:
The UNT Digital Library
Three-dimensional magnetic field produced by an axisymmetric iron yoke
A computational procedure, in which separate analyses are performed for conductor and high permeability iron yoke, has been developed for calculating the three-dimensional magnetic field components. Whereas the field components of the isolated 3-D current array can be evaluated at all desired points through the use of a 3-D Biot-Savart law program, we have developed a method for calculating the supplemental field that will arise as a result of the presence of a surrounding high-permeability magnetic yoke with an axially-symmetric bore. We may speak of this supplemental field as an image field'' although we shall realize that is may be possible in general to attribute it only to a distinctly diffuse distribution of image current'' or magnetic moments. The boundary associated with the image field'' is such that at each point along the boundary of the high permeability iron the total scalar potential shall be constant, e.g. V{sup i} = {minus}V{sup d} (where i=image and d=direct). When we describe both potentials as a series of harmonic components'' then the nature of the boundary condition is such that a de-coupling of one harmonic from another is preserved, and therefore it is also true that V{sup i}(n) = {minus}V{sup d}(n) at the …
Date:
June 1, 1991
Creator:
Laslett, L.J.; Caspi, S.; Helm, M. & Brady, V.
Object Type:
Article
System:
The UNT Digital Library
Electricity Use in the Pacific Northwest: Utility Historical Sales by Sector, 1990 and Preceding Years.
This report officially releases the compilation of regional 1990 retail customer sector sales data by the Bonneville Power Administration. The report is intended to enable detailed examination of annual regional electricity consumption. It also provides observations based on statistics covering the 1983--1990 time period, and gives statistics covering the time period 1970--1990. The electricity use report is the only information source that provides data obtained from each utility in the region based on the amount of electricity they sell annually to four sectors. Data is provided on each retail customer sector and also on the customers Bonneville serves directly: residential, commercial, industrial, direct-service industrial, and irrigation. 21 figs., 40 tabs.
Date:
June 1, 1991
Creator:
United States. Bonneville Power Administration.
Object Type:
Report
System:
The UNT Digital Library
Pacific Northwest Laboratory annual report for 1990 to the DOE Office of Energy Research
This report summarizes progress on OHER human health, biological, and general life sciences research programs conducted at PNL in FY 1990. The research develops the knowledge and scientific principles necessary to identify understand, and anticipate the long-term health consequences of energy-related radiation and chemicals. Our continuing emphasis is to decrease the uncertainty of health risk estimates from existing and developing energy-related technologies through an increased of understanding of how radiation and chemicals cause biological damage. The sequence of this report of PNL research reflects the OHER programmatic structure. The first section, on human health research, concerns epidemiological and statistical studies for assessing health risks. The next section contains reports of biological research in laboratory animals and in vitro cell systems, including research with radionuclides and chemicals. The general life sciences research section reports research conducted for the OHER human genome research program.
Date:
June 1, 1991
Creator:
Park, J. F.
Object Type:
Report
System:
The UNT Digital Library
The University of Minnesota aquifer thermal energy storage (ATES) field test facility -- system description, aquifer characterization, and results of short-term test cycles
Phase 1 of the Aquifer Thermal Energy Storage (ATES) Project at the University of Minnesota was to test the feasibility, and model, the ATES concept at temperatures above 100{degrees}C using a confined aquifer for the storage and recovery of hot water. Phase 1 included design, construction, and operation of a 5-MW thermal input/output field test facility (FTF) for four short-term ATES cycles (8 days each of heat injection, storage, and heat recover). Phase 1 was conducted from May 1980 to December 1983. This report describes the FTF, the Franconia-Ironton-Galesville (FIG) aquifer used for the test, and the four short-term ATES cycles. Heat recovery; operational experience; and thermal, chemical, hydrologic, and geologic effects are all included. The FTF consists of monitoring wells and the source and storage well doublet completed in the FIG aquifer with heat exchangers and a fixed-bed precipitator between the wells of the doublet. The FIG aquifer is highly layered and a really anisotropic. The upper Franconia and Ironton-Galesville parts of the aquifer, those parts screened, have hydraulic conductivities of {approximately}0.6 and {approximately}1.0 m/d, respectively. Primary ions in the ambient ground water are calcium and magnesium bicarbonate. Ambient temperature FIG ground water is saturated with respect to calcium/magnesium …
Date:
June 1, 1991
Creator:
Walton, M.; Hoyer, M. C.; Eisenreich, S. J.; Holm, N. L.; Holm, T. R.; Kanivetsky, R. et al.
Object Type:
Report
System:
The UNT Digital Library
Functional requirements for the Tumulus I and II cap Waste Area Grouping 6 Oak Ridge National Laboratory
The tumulus method of solid low-level waste (LLW) disposal began in 1989 with the Tumulus Disposal Demonstration (TDD) project, conducted on Tumulus I. LLW is contained in 4-ft {times} 4-ft {times} 6-ft boxes which are placed into precast concrete casks. The annular space around the box is grouted with a cementious grout before the lid is installed. The LLW does not contain RCRA materials or liquids. The casks are then stacked two high on the concrete tumulus pad. Prior to filling Tumulus I to capacity Tumulus II was constructed. Tumulus II will be filled to capacity by the end of 1991 at which time the Interim Waste Management Facility (IWMF) will have been constructed and will provide approximately six years of LLW disposal capacity. This project will provide interim closure of the Tumulus I and II by designing and constructing a multilayered cap, with monitoring capabilities, which will be consistent in purpose with the requirements of a Record of Decision (ROD) which will result from the Waste Area Group (WAG) 6 closure and remediation effort. Capping Tumulus I and II has been a part of the overall tumulus disposal plan since inception in the Low Level Waste Disposal, Development and …
Date:
June 1, 1991
Creator:
Cox, L.C.
Object Type:
Report
System:
The UNT Digital Library
Water-table elevations on the Hanford Site, 1990
The Pacific Northwest Laboratory prepared water-table maps of the US Department of Energy's Hanford Site for June 1990 from water-level elevations measured in 224 wells across the Hanford Site. The greatest changes in the elevation of the water table at Hanford occurred beneath the decommissioned U Pond, 200-East Area, the 100-N Area, the 1100 and 3000 Areas, and near the Columbia River. The elevation of the ground-water mound beneath the decommissioned U Pond continued to decline, decreasing as much as 0.8 m (2.6 ft) between December 1989 and December 1990. This decline has been observed in wells in much of the adjacent 200-West Area and is primarily the result of continued dissipation of the ground-water mound beneath U Pond since it was deactivated in 1984. 21 refs., 12 figs.
Date:
June 1, 1991
Creator:
Newcomer, D R; Pohlod, K D & McDonald, J P
Object Type:
Report
System:
The UNT Digital Library
SLC positron source pulsed flux concentrator
SLC positron beams produced by a high energy electron beam, impinging on a high Z target, have initially small transverse size but large divergence, a situation ill matched to the following S-band accelerator. The flux concentrator is an adiabatic matching device placed between the target and this accelerator, which trades divergence versus size. It produces a magnetic field with a sharp rise over less than 5 mm to its peak value, and then falling off adiabatically over 10 cm. It is a 12 turn, 10 cm long copper coil with a cylindrical outside radius of 4 cm and a conical inside radius growing from 3.5 mm to 2.6 cm. The 0.2 mm gaps between the individual windings were manufactured by electric discharge machining out of one copper block. Excitation current and water cooling is provided by a hollow rectangular copper conductor brazed to the outside of the coil (also 12 turns). The pulsed magnetic field has a maximum strength of 58 kG at 16 kA. At the terminals, the coil has an inductance of 0.8 {mu}H. Current shape is a half sinusoidal wave with a bottom width of 5 {mu}s, and the system operates at a repetition rate of 120 …
Date:
June 1, 1991
Creator:
Kulikov, A.V.; Ecklund, S.D. & Reuter, E.M.
Object Type:
Article
System:
The UNT Digital Library
Beamstrahlung simulation and diagnostics
A simulation code that models the mutual deflection and the emission of beamstrahlung of two ultra-relativistic electron and positron bunches is described. The simulations are used to determine transverse beam sizes from observed beamstrahlung fluxes. 8 refs., 3 figs.
Date:
June 1, 1991
Creator:
Ziemann, V.
Object Type:
Article
System:
The UNT Digital Library
Some design considerations for pbar target sweeping station
This report summarizes the results of some recent calculations useful to design the beam sweeping station to produce high intensity pbar beam at AP0. With various on-going and planned intensity upgrade at the accelerator including the main injector the primary beam intensity on the pbar target is expected to increase. But some complications would arise from the existing method of pbar production. A study of the heavy metal targets used when the beam intensity was about 1.0 {times} 10{sup 12}, has shown a clear indication of target destruction by the proton beam. Although the heavy metal has very high melting point temperature the thermoelastic property is not suitable for its use as a reliable pbar target. During 1989 collider run, the target material was changed over to copper because of its better thermoelastic properties. The pbar yield measurement did not show much indications of target destruction except for a small decrease in the pbar yield. However, the calculations showed that the target material along the beam might have had enough energy deposition to transform the target material from the solid state to the liquid state during the beam spill time. A further increase of the proton beam intensity might cause …
Date:
June 1, 1991
Creator:
Bhat, C.M.
Object Type:
Report
System:
The UNT Digital Library
Uniform remote control of front end processors in PAN-DA
The PAN-DA data acquisition software system encompasses support for a variety of front end processors including the Struck General Purpose Master (GPM), the Fermilab Smart Crate Controller (FSCC), and the Motorola MVME133-A VME single board computer. PAN-DA provides support for the remote control of these processors through its Remote Procedure eXecution (RPX) software. This software runs over serial lines, and in some PAN-DA environments, over the Ethernet and TCP/IP as well. Experiments E791 and E771 have successfully used RPX software in both FSCC software development and data collection during the 1990--1991 fixed target run at Fermilab. RPX software has facilitated development and testing of the Fermilab Silicon Strip Detector readout system, for which the FSCC is an integral component. RPX based control and monitoring of the GPM and the MVME133-A are essential parts of the PAN-DA data acquisition system used by E687 and E773 during the 1990--1991 run. 6 refs., 2 figs.
Date:
June 1, 1991
Creator:
Berg, D.; Berman, E.; MacKinnon, B.; Nicinski, T.; Oleynik, G.; Petravick, D. et al.
Object Type:
Article
System:
The UNT Digital Library
An investigation of dual-mode operation of a nuclear-thermal rocket engine
A preliminary assessment of the technical feasibility and mass competitiveness of a dual-mode nuclear propulsion and power system based on Rover-type reactors has been completed. Earlier studies have indicated that dual-mode systems appear attractive for electrical power levels of a few kilowatts. However, at the megawatt electrical power level considered in this study, it appears that extensive modifications to the nuclear-thermal engines would be required, the feasibility of which is unclear. Mass competitiveness at high electrical power levels is also uncertain. Further study of reactor and shield design in conjuction with mission and vehicle studies is necessary in order to determine a useful dual-mode power range. 9 refs., 20 figs., 4 tabs.
Date:
June 1, 1991
Creator:
Kirk, W. L.; Hedstrom, J. C.; Moore, S. W.; McFarland, R. D.; Merrigan, M. A.; Buksa, J. J. et al.
Object Type:
Report
System:
The UNT Digital Library
Progress in AMS measurements at the LLNL spectrometer. [Accelerator Mass Spectroscopy (AMS)]
The AMS measurement program at LLNL began in earnest in late 1989, and has initially concentrated on {sup 14}C measurements for biomedical and geoscience applications. We have now begun measurements on {sup 10}Be and {sup 36}Cl, are presently testing the spectrometer performance for {sup 26}Al and {sup 3}H, and will begin tests on {sup 7}Be, {sup 41}Ca and {sup 129}I within the next few months. Our laboratory has a strong biomedical AMS program of {sup 14}C tracer measurements involving large numbers of samples (sometimes hundreds in a single experiment) at {sup 14}C concentrations which are typically .5--5 times Modern, but are occasionally highly enriched. The sample preparation techniques required for high throughput and low cross-contamination for this work are discussed elsewhere. Similar demands are placed on the AMS measurement system, and in particular on the ion source. Modifications to our GIC 846 ion source, described below, allow us to run biomedical and geoscience or archaeological samples in the same source wheel with no adverse effects. The source has a capacity for 60 samples (about 45 unknown) in a single wheel and provides currents of 30--60{mu}A of C{sup {minus}} from hydrogen-reduced graphite. These currents and sample capacity provide high throughput for …
Date:
June 1, 1991
Creator:
Southon, J. R.; Vogel, J. S.; Trumbore, S. E.; Davis, J. C.; Roberts, M. L.; Caffee, M. et al.
Object Type:
Article
System:
The UNT Digital Library
Strange quarks in nuclei
We survey the field of strange particle nuclear physics, starting with the spectroscopy of strangeness S = {minus}1 {Lambda} hypernuclei, proceeding to an interpretation of recent data on S = {minus}2 {Lambda}{Lambda} hypernuclear production and decay, and finishing with some speculations on the production of multi-strange nuclear composites (hypernuclei or strangelets'') in relativistic heavy ion collisions. 41 refs., 5 figs.
Date:
June 1, 1991
Creator:
Dover, C. B.
Object Type:
Article
System:
The UNT Digital Library
Estimation of fracture toughness of cast stainless steels during thermal aging in LWR systems
A procedure and correlations are presented for predicting the change in fracture toughness of cast stainless steel components due to thermal aging during service in light water rectors (LWRs) at 280--330{degrees}C (535--625{degrees}F). The fracture toughness J-R curve and Charpy-impact energy of aged cast stainless steels are estimated from known mineral in formation. Fracture toughness of a specific cast stainless steel is estimated from the extent and kinetics of thermal embrittlement. The extent of thermal embrittlement is characterized by the room-temperature normalized'' Charpy-impact energy. A correlation for the extent of embrittlement at saturation,'' i.e., the minimum impact energy that would be achieved for the material after long-term aging, is given in terms of a material parameter, {Phi}, which is determined from the chemical composition. The fracture toughness J-R curve for the material is then obtained from correlations between room-temperature Charpy-impact energy and fracture toughness parameters. Fracture toughness as a function of time and temperature of reactor service is estimated from the kinetics of thermal embrittlement, which is determined from chemical composition. A common lower-bound'' J-R curve for cast stainless steels with unknown chemical composition is also defined for a given material specification, ferrite content, and temperature. Examples for estimating impact strength …
Date:
June 1, 1991
Creator:
Chopra, O.K. (Argonne National Lab., IL (USA))
Object Type:
Report
System:
The UNT Digital Library
Scanning tunneling microscopy studies of the surfaces of a-Si:H and a-SiGe:H films
The report contains a detailed description of the experimental complexities encountered in developing scanning tunneling microscope (STM) probing of atomic structure on the surface of freshly-grown hydrogenated-amorphous semiconductors. It also contains a speculative microscopic film-growth model that explains differences between the disorder in CVD grown a-Ge:H versus a-Si:H films. This model is derived from prior results obtained in the chemical analysis of GeH{sub 4} plasmas, combined with surface reaction and thermodynamic considerations. The neutral radical fragments of silane, disilane and germane dissociation in discharges, which dominate the vapor and film-growth reactions, have been deduced from detailed analysis of prior data and are reported. 4 refs., 7 figs.
Date:
June 1, 1991
Creator:
Gallagher, A.; Ostrom, R. & Tannenbaum, D. (National Inst. of Standards and Technology, Boulder, CO (USA))
Object Type:
Report
System:
The UNT Digital Library
Single-shell tank constituent rankings for use in preparing waste characterization plans
Waste characterization efforts for underground single-shell tanks (SSTs) containing chemical and radioactive mixed wastes at the US Department of Energy's (DOE) Hanford Site are currently under way. As a component of this effort, an analysis was conducted to give a preliminary ranking of possible constituents in the SST waste and provide data for establishing detection limit requirements for the SST characterization effort. These SST constituent rankings were based on a relative comparison using potential human health impacts modeled using a hypothetical exposure scenario. This modeling effort used preliminary estimates of the SST inventories, simplified estimates of constituent release rates and environmental transport, a hypothetical usage location, and a standard Hanford exposure scenario. The results of this evaluation are SST constitutents for each of six groups of SSTs ranked according to their relative potential for impacts. The relative rankings for different recharge rates at the tank farms were nearly equivalent. Sensitivity tests demonstrated that the rankings are influenced by changes in recharge and transport parameters. 45 refs., 18 figs., 2 tabs.
Date:
June 1, 1991
Creator:
Droppo Jr., J. G.; Buck, J. W.; Wilbur, J. S.; Strenge, D. L. & Freshley, M. D.
Object Type:
Report
System:
The UNT Digital Library
Plutonium isotopic analysis system for plutonium samples enriched in sup 238 Pu in EP 60/61 containers
This hardware manual is addressed to Savannah River Site supervisors and to authorized mechanical and electrical maintenance and service personnel. Each chapter begins with a table of contents that lists the section titles, illustrations, and tabular data presented in that chapter. The first chapter in this manual is an introduction to the Pu-238 isotopic analysis system. Chapter 2 lists major components of the system and includes electronic block and wiring diagrams. Commercial nuclear instrument modules and their required settings are described in Chapter 3. Chapter 4 contains service and preventive maintenance procedures, as well as a troubleshooting log. In Chapter 5 is a list of spare parts and all relevant mechanical drawings for the system. Chapter 6 contains reference articles. All commercial items mentioned in this manual are assumed to be functioning correctly for the purposes of system operation. Users are referred to individual equipment manufacturers' manuals for details of operation, troubleshooting, and maintenance of this commercial equipment. 31 figs., 1 tab.
Date:
June 1, 1990
Creator:
Ruhter, W. D.; DeWitt, K. W.; Pederson, K. B. & Watkins, J. A.
Object Type:
Report
System:
The UNT Digital Library
Measurements of magnetization multipoles in four centimeter quadrupoles for the SSC
Higher multipoles due to magnetization of the superconductor in superconducting dipole and quadrupole magnets has been observed in over twenty years. This report presents measurements of the 12 pole and 20 pole multipoles in a model one-meter long four-centimeter bore SSC type quadrupole built at the Lawrence Berkeley Laboratory (LBL). The measurements were compared with calculations of the field structure using magnetization theory. Good agreement was observed between the measured multipoles and the calculated multipoles. Under conditions equivalent to injection into the SSC at an energy of 2 TeV, about 1.0 unit of 12 pole was observed and 0.05 units of 20 pole was observed. (One unit of field error is a field error of one part in ten thousand). Magnetization multipole measurements were also done on the first full length (5 meter) SSC quadrupole prototype. Measurements of flux creep decay were made on three one meter quadrupoles and the first five meter long quadrupole. 7 refs., 9 figs.
Date:
June 1, 1991
Creator:
Green, M. A.; Barale, P. J.; Benjegerdes, R. W.; Gilbert, W. S.; Green, M. I.; Scanlan, R. M. et al.
Object Type:
Article
System:
The UNT Digital Library
Development of Alaskan Gas Hydrate Resources
The research undertaken in this project pertains to study of various techniques for production of natural gas from Alaskan gas hydrates such as, depressurization, injection of hot water, steam, brine, methanol and ethylene glycol solutions through experimental investigation of decomposition characteristics of hydrate cores. An experimental study has been conducted to measure the effective gas permeability changes as hydrates form in the sandpack and the results have been used to determine the reduction in the effective gas permeability of the sandpack as a function of hydrate saturation. A user friendly, interactive, menu-driven, numerical difference simulator has been developed to model the dissociation of natural gas hydrates in porous media with variable thermal properties. A numerical, finite element simulator has been developed to model the dissociation of hydrates during hot water injection process.
Date:
June 1, 1991
Creator:
Kamath, V. A.; Sharma, G. D. & Patil, S. L.
Object Type:
Report
System:
The UNT Digital Library
TMI-2 Vessel Investigation Project (VIP) Metallurgical Program
The TMI-2 Vessel Investigation Project (VIP) Metallurgical Program is a part of the international TMI-2 Vessel Investigation Project being conducting jointly by the US Nuclear Regulatory Commission and the Organization for Economic Co-operation and Development (OECD). The overall project consists of three phases, namely (1) recovery of material samples from the lower head of the TMI-2 reactor, (2) examination and analysis of the lower head samples and the preparation and testing of archive material subjected to a similar thermal history, and (3) procurement, examination, and analysis of companion core material located adjacent to or near the lower head material. The specific objectives of the ANL Metallurgical Program, which comprises a major portion of Phase 2, are to prepare metallographic and mechanical test specimen blanks from the TMI-2 lower head material, prepare similar test specimen blanks from suitable archive material subjected to the appropriate thermal processing, determine the mechanical properties of the lower vessel head and archive materials under the conditions of the core-melt accident, and assess the lower head integrity and margin-to-failure during the accident. The ANL work consists of three tasks: (1) archive materials program, (2) fabrication of metallurgical and mechanical test specimens from the TMI-2 pressure vessel samples, …
Date:
June 1, 1990
Creator:
Diercks, D. R. & Neimark, L. A.
Object Type:
Article
System:
The UNT Digital Library
Energy Edge, Post-Occupancy Evaluation Project: The Eastgate Corporate Center Bellevue, Washington
The Workspace Satisfaction Survey measures occupant satisfaction with the thermal, lighting, acoustical, and air quality aspects of the work environment. In addition to ratings of these ambient environmental features, occupants also rate their satisfaction with a number of functional and aesthetic features of the office environment as well as their satisfaction with specific kinds of workspaces (e.g. computer rooms, the lobby, employee lounge, etc.) Each section on ambient conditions includes questions on the frequency with which people experience particular kinds of discomforts or problems, how much the discomfort bothers them, and how much it interferes with their work. Occupants are also asked to identify how they cope with discomfort or environmental problems, and to what extent these behaviors enable them to achieve more satisfactory conditions. This report documents the results of this survey of the occupants of the Eastgate Corporate Center, Bellevue, Washington. 21 figs., 7 tabs.
Date:
June 1, 1990
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
An idealized transient model for melt dispersal from reactor cavities during pressurized melt ejection accident scenarios
The direct Containment Heating (DCH) calculations require that the transient rate at which the melt is ejected from the reactor cavity during hypothetical pressurized melt ejection accident scenarios be calculated. However, at present no models, that are able to predict the available melt dispersal data from small scale reactor cavity models, are available. In this report, a simple idealized model of the melt dispersal process within a reactor cavity during a pressurized melt ejection accident scenario is presented. The predictions from the model agree reasonably well with the integral data obtained from the melt dispersal experiments using a small scale model of the Surry reactor cavity. 17 refs., 15 figs.
Date:
June 1, 1991
Creator:
Tutu, N.K.
Object Type:
Report
System:
The UNT Digital Library