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[Abilene City Ordinances: 1998]
Ledger containing ordinances/resolutions passed by the city of Abilene, Texas during calendar year 1998.
Date:
1998
Creator:
Abilene (Tex.)
Object Type:
Legal Document
System:
The Portal to Texas History
[Abilene City Resolutions: 1998]
Ledger containing resolutions passed by the city of Abilene, Texas during calendar year 1998.
Date:
1998
Creator:
Abilene (Tex.)
Object Type:
Legal Document
System:
The Portal to Texas History
[Program: My Fair Lady, 1998]
Program for a production of My Fair Lady at Abilene Christian University performed at the Abilene Civic Center Theatre from October 16th to 18th, 1998. It includes a list of cast and staff, and other information about the play.
Date:
1998
Creator:
Abilene Christian College
Object Type:
Pamphlet
System:
The Portal to Texas History
Catalog of Abilene Christian University, 1998-1999
Undergraduate catalog describes the governance, history, academic programs, course descriptions, and campus life of Abilene Christian University in Abilene, Texas.
Date:
1998
Creator:
Abilene Christian University
Object Type:
Book
System:
The Portal to Texas History
Prickly Pear, Yearbook of Abilene Christian University, 1998
Yearbook for Abilene Christian University in Abilene, Texas includes photos of and information about the school, student body, professors, and organizations. Index starts on page 312.
Date:
1998
Creator:
Abilene Christian University
Object Type:
Yearbook
System:
The Portal to Texas History
The Shinnery Review, Volume 57, 1998
The Shinnery Review literary magazine of Abilene Christian University includes original short stories, essays, poetry, artwork, and other creative works.
Date:
1998
Creator:
Abilene Christian University
Object Type:
Journal/Magazine/Newsletter
System:
The Portal to Texas History
Abilene Philharmonic Playbill: February 28-March 21, 1998
Program for Abilene Philharmonic concerts performed on February 28th (fifth concert, classical) and March 21st (sixth concert, pops) during the 48th season. It includes information about the pieces performed, artists and musicians, and advertising from local companies.
Date:
February 1998
Creator:
Abilene Philharmonic
Object Type:
Book
System:
The Portal to Texas History
Abilene Philharmonic Playbill: April 18-May 2, 1998
Program for Abilene Philharmonic concerts performed on April 18th (seventh concert, classical) and May 2nd (eighth concert, classical) during the 48th season. It includes information about the pieces performed, artists and musicians, and advertising from local companies.
Date:
April 1998
Creator:
Abilene Philharmonic
Object Type:
Book
System:
The Portal to Texas History
Abilene Philharmonic Playbill: September 19-October 31, 1998
Program for an Abilene Philharmonic concert that ran from September 19th to October 31st (Classical I and Pops I) during the 49th season. It includes information about the pieces performed, artists and musicians, and advertising from local companies.
Date:
September 1998
Creator:
Abilene Philharmonic
Object Type:
Pamphlet
System:
The Portal to Texas History
Abilene Philharmonic Playbill: December 5-January 30, 1999
Program for an Abilene Philharmonic concert that ran from December 5th, 1998 to January 30th during the 49th season. It includes information about the pieces performed, artists and musicians, and advertising from local companies.
Date:
December 1998
Creator:
Abilene Philharmonic
Object Type:
Pamphlet
System:
The Portal to Texas History
Corrosion testing of stainless steel-zirconium metal waste form.
Stainless steel-zirconium (SS-Zr) alloys are being considered as waste forms for the disposition of metallic waste generated during the electrometallurgical treatment of spent nuclear fuel. The waste forms contain irradiated cladding hulls, components of the alloy fuel, noble metal fission products, and actinide elements. The baseline waste form is a stainless steel-15 wt% zirconium (SS-15Zr) alloy. This article presents microstructure and some of the corrosion studies being conducted on the waste form alloys. Electrochemical corrosion, immersion corrosion, and vapor hydration tests have been performed on various alloy compositions to evaluate corrosion behavior and resistance to selective leaching of simulated fission products. The SS-Zr waste forms are successful at the immobilization and retention of fission products and show potential for acceptance as high-level nuclear waste forms.
Date:
December 14, 1998
Creator:
Abraham, D. P.
Object Type:
Article
System:
The UNT Digital Library
Metal waste forms from treatment of EBR-II spent fuel.
Demonstration of Argonne National Laboratory's electrometallurgical treatment of spent nuclear fuel is currently being conducted on irradiated, metallic driver fuel and blanket fuel elements from the Experimental Breeder Reactor-II (EBR-II) in Idaho. The residual metallic material from the electrometallurgical treatment process is consolidated into an ingot, the metal waste form (MWF), by employing an induction furnace in a hot cell. Scanning electron microscopy (SEM) and chemical analyses have been performed on irradiated cladding hulls from the driver fuel, and on samples from the alloy ingots. This paper presents the microstructures of the radioactive ingots and compares them with observations on simulated waste forms prepared using non-irradiated material. These simulated waste forms have the baseline composition of stainless steel - 15 wt % zirconium (SS-15Zr). Additions of noble metal elements, which serve as surrogates for fission products, and actinides are made to that baseline composition. The partitioning of noble metal and actinide elements into alloy phases and the role of zirconium for incorporating these elements is discussed in this paper.
Date:
May 18, 1998
Creator:
Abraham, D. P.
Object Type:
Article
System:
The UNT Digital Library
Descriptors for solutes from the solubility of solids: trans-stilbene as an example
Article on descriptors for solutes from the solubility of solids and trans-stilbene as an example.
Date:
1998
Creator:
Abraham, M. H. (Michael H.); Green, Caroline E.; Acree, William E. (William Eugene); Hernández, Carmen E. & Roy, Lindsay Elizabeth
Object Type:
Article
System:
The UNT Digital Library
Model Etch Profiles for Ion Energy Distribution Functions in an Inductively Coupled Plasma Reactor
Rectangular trench profiles are modeled with analytic etch rates determined from measured ion distribution functions. The pattern transfer step for this plasma etch is for trilayer lithography. Argon and chlorine angular ion energy distribution functions measured by a spherical collector ring analyzer are fit to a sum of drifting Maxwellian velocity distribution functions with anisotropic temperatures. The fit of the model ion distribution functions by a simulated annealing optimization procedure converges adequately for only two drifting Maxwellians. The etch rates are proportional to analytic expressions for the ion energy flux. Numerical computation of the etch profiles by integration of the characteristic equations for profile points and connection of the profiles points is efficient.
Date:
December 14, 1998
Creator:
Abraham-Shrauner, B.; Chen, W. & Woodworth, J.R.
Object Type:
Article
System:
The UNT Digital Library
U.S./Russian cooperative efforts to enhance nuclear MPC&A at VNIITF, (Chelyabinsk-70)
The All Russian Scientific Research Institute of Technical Physics (VNIITF) is one of the major sites in the nuclear weapons complex in Russia. The site contains a number of research facilities which use nuclear material as well as assembly, disassembly, and testing of prototypes (pilot samples) of nuclear weapons. VNIITF also has ties to the major nuclear materials production facilities in the Urals region of Russia. The objective of the U.S./Russian Materials Protection Control and Accounting (MPC&A) cooperative program between the US Department of Energy and Russia�s Ministry of Atomic Eneryy, at VNIITF is to improve the protection and accountability of nuclear material at VNIITF. Enhanced safeguards systems have been implemented at a reactor test area called the Pulse Research Reactor Facility (PRR) in Area 20. The area contains three pulse reactors with associated storage areas. The integrated MPC&A system at the PRR was demonstrated to US and Russian audiences in May, 1998. Expansion of work into several new facilities is underway both in Area 20 and at other locations. These include processing and production facilities some of which are considered sensitive facilities, by the Russian side. Methods have been developed to assure that work is done as agreed without …
Date:
September 1, 1998
Creator:
Abramson, B.; Apt, K.; Blasy, J.; Bukin, D.; Churikov, Y.; Eras, A. et al.
Object Type:
Article
System:
The UNT Digital Library
A study of the elasticity of Ta at high temperature and pressure
The thermodynamic and transport properties of crystals and fluids at high temperature and pressure play a central role in the Earth and planetary sciences as well as in a variety of technologies and constitute a principal probe into the internuclear potential energy function at high density. Observation of surface waves by coherent time-domain optical spectroscopy provides an experimental approach to the determination, in the diamond-anvil high-pressure cell, of the elastic constants and thermal diffusivity of metal crystals as well as the equation of state and thermal transport properties of fluids. The electrical resistivities of metals may also be approximately accessible via the Wiedemann Franz Law. Preliminary results on Ta to pressures of 5.2 GPa are reported here. [Ta, elasticity, sound velocity, thermal diffusivity, equation of state].
Date:
August 26, 1998
Creator:
Abramson, E H; Brown, J M; Hansen, D W; Ruddle, C M; Slutsky, L J & Zaug, J M
Object Type:
Article
System:
The UNT Digital Library
Drying behavior of K-East canister sludge
A series of tests were conducted by Pacific Northwest National Laboratory to evaluate the drying behavior of sludge taken from the Hanford K-East Basin storage canisters. Some of the components of K-Basin sludge, such as oxides of uranium and its hydrates, could be associated with the spent nuclear fuel that will ultimately be loaded into Multi-Canister Overpacks (MCOs) and transferred to interim dry storage on the Hanford Site. The materials sealed in the MCOs must be compatible with the storage facility safety basis and the design accident analyses. Understanding the drying behavior of hydrates that may be formed by the reaction of uranium oxides (corrosion products) and water will help ensure these criteria are addressed. Drying measurements of sludge samples collected from K-East Basin canisters showed the water content (physically plus chemically bound) to range between 5 wt% and 75 wt%. Uranium oxide hydrates, the main source of gaseous products that can pressurize the MCOs during storage, constituted about 3 wt% to 15 wt% of the total water content of the initial weight. Most of the physically bound water was assumed to be released from the samples at ambient temperature when the system was pumped down to vacuum conditions of …
Date:
May 1, 1998
Creator:
Abrefah, J.; Buchanan, H. C. & Marschman, S. C.
Object Type:
Report
System:
The UNT Digital Library
Oxidation rate of K-Basin spent nuclear fuel in moist air
Experiments have been conducted by Pacific Northwest National Laboratory to determine the oxidation rate of damaged/corroded N-Reactor fuel material in moist air. Five SNF pieces (with regular geometrical shapes) sectioned from a damaged element stored in the K-West Basin were oxidized in flowing air containing moisture. The SNF oxidation behavior in moist air at a temperature of 198 C can best be fitted by parabolic oxidation kinetics. A linear rate equation gave the best fit to the oxidation data at 250 C and above. The results within the temperature range studied, therefore, show a transition from parabolic oxidation kinetics to linear oxidation kinetics. The transition temperature is somewhere between 198 C and 250 C. The tests at approximately 300 C gave results that were very different from the other tests at temperatures of 198 C, 250 C, and 349 C. The SNF sample weight change at this temperature showed erratic behavior. Visual examination indicated the sample fragmented into small pieces and powder as a result of rapid oxidation and hydration. Additional tests at temperatures close to 300 C (i.e., 300 {+-} 10 C) are recommended in order to fully understand the oxidation behavior of the damaged/corroded SNF samples in moist …
Date:
June 1, 1998
Creator:
Abrefah, J.; Buchanan, H. C. & Marschman, S. C.
Object Type:
Report
System:
The UNT Digital Library
Dry air oxidation kinetics of K-Basin spent nuclear fuel
The safety and process analyses of the proposed Integrated Process Strategy (IPS) to move the N-Reactor spent nuclear fuel (SNF) stored at K-Basin to an interim storage facility require information about the oxidation behavior of the metallic uranium. Limited experiments have been performed on the oxidation reaction of SNF samples taken from an N-Reactor outer fuel element in various atmospheres. This report discusses studies on the oxidation behavior of SNF using two independent experimental systems: (1) a tube furnace with a flowing gas mixture of 2% oxygen/98% argon; and (2) a thermogravimetric system for dry air oxidation.
Date:
June 1, 1998
Creator:
Abrefah, J.; Buchanan, H. C.; Gerry, W. M.; Gray, W. J. & Marschman, S. C.
Object Type:
Report
System:
The UNT Digital Library
Drying results of K-Basin fuel element 3128W (run 2)
An N-Reactor outer fuel element that had been stored underwater in the Hanford 100 Area K-East Basin was subjected to a combination of low- and high-temperature vacuum drying treatments. These studies are part of a series of tests being conducted by Pacific Northwest National Laboratory on the drying behavior of N-Reactor spent nuclear fuel elements removed from both the K-West and K-East Basins. The drying test series was designed to test fuel elements that ranged from intact to severely damaged. The fuel element discussed in this report was removed from an open K-East canister (3128W) during the first fuel selection campaign conducted in 1995, and has remained in wet storage in the Postirradiation Testing Laboratory (PTL, 327 Building) since that time. Although it was judged to be breached during in-basin (i.e., K-Basin) examinations, visual inspection of this fuel element in the hot cell indicated that it was likely intact. Some scratches on the coating covering the cladding were identified before the furnace test. The drying test was conducted in the Whole Element Furnace Testing System located in G-Cell within the PTL. This test system is composed of three basic systems: the in-cell furnace equipment, the system gas loop, and the …
Date:
July 1, 1998
Creator:
Abrefah, J.; Klinger, G. S.; Oliver, B. M.; Marshman, S. C.; MacFarlan, P. J.; Ritter, G. A. et al.
Object Type:
Report
System:
The UNT Digital Library
Examination of the surface coating removed from K-East Basin fuel elements
This report provides the results of studies conducted on coatings discovered on the surfaces of some N-Reactor spent nuclear fuel (SNF) elements stored at the Hanford K-East Basin. These elements had been removed from the canisters and visually examined in-basin during FY 1996 as part of a series of characterization tests. The characterization tests are being performed to support the Integrated Process Strategy developed to package, dry, transport, and store the SNF in an interim storage facility on the Hanford site. Samples of coating materials were removed from K-East canister elements 2350E and 2540E, which had been sent, along with nine other elements, to the Postirradiation Testing Laboratory (327 Building) for further characterization following the in-basin examinations. These coating samples were evaluated by Pacific Northwest National Laboratory using various analytical methods. This report is part of the overall studies to determine the drying behavior of corrosion products associated with the K-Basin fuel elements. Altogether, five samples of coating materials were analyzed. These analyses suggest that hydration of the coating materials could be an additional source of moisture in the Multi-Canister Overpacks being used to contain the fuel for storage.
Date:
May 1, 1998
Creator:
Abrefah, J.; Marschman, S.C. & Jenson, E.D.
Object Type:
Report
System:
The UNT Digital Library
The migration and entrapment of DNAPLs in physically and chemically heterogeneous porous media. 1998 annual progress report
'The migration and entrapment of dense nonaqueous phase liquids (DNAPLs) at hazardous waste sites is typically believed to be controlled by physical heterogeneities. This belief is based upon the assumption that permeability and capillary properties are determined by soil texture. These transport properties however, also depend on porous media wettability characteristics, which may vary spatially in a formation due to variations in aqueous phase chemistry, contaminant aging, and/or variations in mineralogy and organic matter distributions. The overall objective of this research is to investigate the influence of such coupled physical and chemical heterogeneities on the migration and entrapment of DNAPLs in the saturated zone. This research includes laboratory and numerical investigations for a matrix of organic contaminants and solid media encompassing a range of wettability characteristics. Specific objectives include: (1) quantification of system wettability and interfacial tensions; (2) determination of transport property relations; (3) two-dimensional infiltration experiments; (4) modification of a continuum based multiphase flow simulator to account for physical heterogeneity, saturation independent and saturation dependent wettability, and concentration dependent wettability and interfacial tension; and (5) utilization of this model to explore the potential influence of coupled physical and chemical heterogeneities on the migration of DNAPLs and the development of …
Date:
June 1, 1998
Creator:
Abriola, L.M. & Demond, A.H.
Object Type:
Report
System:
The UNT Digital Library
Coupling 2-D cylindrical and 3-D x-y-z transport computations
This paper describes a new two-dimensional (2-D) cylindrical geometry to three-dimensional (3-D) rectangular x-y-z splice option for multi-dimensional discrete ordinates solutions to the neutron (photon) transport equation. Of particular interest are the simple transformations developed and applied in order to carry out the required spatial and angular interpolations. The spatial interpolations are linear and equivalent to those applied elsewhere. The angular interpolations are based on a high order spherical harmonics representation of the angular flux. Advantages of the current angular interpolations over previous work are discussed. An application to an intricate streaming problem is provided to demonstrate the advantages of the new method for efficient and accurate prediction of particle behavior in complex geometries.
Date:
June 30, 1998
Creator:
Abu-Shumays, I. K.; Yehnert, C. E. & Pitcairn, T. N.
Object Type:
Article
System:
The UNT Digital Library
Investigation of Deep Levels in GaInNas
This paper presents and discusses the first Deep-Level transient spectroscopy (DLTS) data obtained from measurements carried out on both Schottky barriers and homojunction devices of GaInNAs. The effect of N and In doping on the electrical properties of the GaNInAs devices, which results in structural defects and interface states, has been investigated. Moreover, the location and densities of deep levels related to the presence of N, In, and N+In are identified and correlated with the device performance. The data confirmed that the presence of N alone creates a high density of shallow hole traps related to the N atom and structural defects in the device. Doping by In, if present alone, also creates low-density deep traps (related to the In atom and structural defects) and extremely deep interface states. On the other hand, the co-presence of In and N eliminates both the interface states and levels related to structural defects. However, the device still has a high density of the shallow and deep traps that are responsible for the photocurrent loss in the GaNInAs device, together with the possible short diffusion length.
Date:
November 12, 1998
Creator:
Abulfotuh, F.; Balcioglu, A.; Friedman, D.; Geisz, J. & Kurtz, S.
Object Type:
Article
System:
The UNT Digital Library