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[Murchison Performing Center-opening gala]

Description: Video footage of the One O'Clock Lab band, wind symphony with grand chorus, and symphony orchestra with grand chorus performing at the Murchison Performing Arts Center opening gala. The video ends with a fireworks display.
Date: February 20, 1999
Creator: Center for Media Production
Partner: UNT Libraries Special Collections

Process modeling of hydrothermal treatment of municipal solid waste to form high solids slurries in a pilot scale system

Description: Two models are developed for characterizing the hydrothermal decomposition of municipal solid waste (MSW) in a pilot scale facility. The process modeled involves the use of high pressure steam to directly heat surrogate MSW, newspaper, to temperatures and pressures where decomposition reactions breakdown the organic matter to form a coal like solid having properties which make it suitable as a feedstock for a commercial gasifier. One model uses the ASPEN steady-state simulator. This model is only capable of computing a limited number of process variables. To more adequately deal with the transient behavior of the inherently batch process a second transient model is formulated. The model allows important process temperatures, pressures, gas flows and compositions to be calculated as a function of time. The model has been used to scope possible operating scenarios for proposed pilot scale experiments and these results are presented. Based on computed results a recommendation is made that the first pilot experiment use a dampened feed material containing a water-to-dry newspaper ratio of 0.5 to 1. The transient model predicts that this will result in a slurry product in the reactor vessel after cooldown containing 57 wt.% water.
Date: February 16, 1995
Creator: Thorsness, C.B.
Partner: UNT Libraries Government Documents Department

Materials Sciences programs, Fiscal year 1993

Description: 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
Partner: UNT Libraries Government Documents Department

Numerical relativity in a distributed environment.

Description: We have found that the hardware and software infrastructure exists to simulate general relativity problems in a distributed computational environment, at some cost in performance. We examine two different issues for running the Cactus code in such a distributed environment The first issue is running a Cactus simulation on multiple parallel computer systems. Our objective is to perform larger simulations than are currently possible on a single parallel computer. We distribute Cactus simulations across multiple supercomputers using the mechanisms provided by the Globus toolkit. In particular, we use Globus mechanisms for authentication, access to remote computer systems, file transfer, and communication. The Cactus code uses MPI for communication and makes use of an MPI implementation layered atop Globus communication mechanisms. These communication mechanisms allow a MPI application to be executed on distributed resources. We find that without performing any code optimizations, our simulations ran 48% to 100% slower when using an Origin at the National Center for Supercomputing Applications (NCSA) and an Onyx2 at Argonne National Laboratory (ANL). We also ran simulations between Cray T3Es in Germany and a T3E at the San Diego Supercomputing Center (SDSC). Running between the T3Es in Germany resulted in an increase in execution time of 79% to 133%, and running between a German T3E and a T3E at the San Diego Supercomputing Center resulted in an execution time increase of 114% to 186%. We are very encouraged that we are able to run simulations on parallel computers that are geographically distributed, and we have identified several areas to investigate to improve the performance of Cactus simulations in this environment. The second issue we examine here is remote visualization and steering of the Cactus code. Cactus is a modular framework and we have implemented a module for this task. This module performs isosurfacing operations on ...
Date: February 8, 1999
Creator: Benger, W.; Foster, I.; Novotny, J.; Seidel, E.; Shalf, J.; Smith, W. et al.
Partner: UNT Libraries Government Documents Department

MIxed Waste Integrated Program (MWIP): Technology summary

Description: The mission of the Mixed Waste Integrated Program (MWIP) is to develop and demonstrate innovative and emerging technologies for the treatment and management of DOE`s mixed low-level wastes (MLLW) for use by its customers, the Office of Waste Operations (EM-30) and the Office of Environmental Restoration (EM-40). The primary goal of MWIP is to develop and demonstrate the treatment and disposal of actual mixed waste (MMLW and MTRU). The vitrification process and the plasma hearth process are scheduled for demonstration on actual radioactive waste in FY95 and FY96, respectively. This will be accomplished by sequential studies of lab-scale non-radioactive testing followed by bench-scale radioactive testing, followed by field-scale radioactive testing. Both processes create a highly durable final waste form that passes leachability requirements while destroying organics. Material handling technology, and off-gas requirements and capabilities for the plasma hearth process and the vitrification process will be established in parallel.
Date: February 1, 1994
Partner: UNT Libraries Government Documents Department

Alaska Power Administration Federal Power Program financial statements with supplementary information September 30, 1994 and September 30, 1993 with auditors` reports thereon

Description: The attached report presents the results of our audit of the Department of Energy`s Alaska Power Administration (APA) financial statements as of September 30, 1994. In our opinion, the APA statements are fairly presented in all material respects in accordance with generally accepted accounting principles. our reports on the APA internal control structure and on its compliance with laws and regulations are also provided. The US Government, through the Department of Energy, operates APA at two sites to provide hydroelectric power to Juneau and Anchorage, Alaska. Additional information about APA is provided in the notes to the financial statements. The 1994 financial statement audit was made under provisions of the Inspector General Act (5 USC. App.), as amended, the Chief Financial Officers (CFO) Act (31 USC 1500) and the Office of Management and Budget implementing guidance to the CFO Act. The auditors` work was conducted in accordance with generally accepted government auditing standards.
Date: February 13, 1995
Partner: UNT Libraries Government Documents Department

Gas and liquid sampling for closed canisters in KW Basin - Work Plan

Description: Work Plan for the design and fabrication of gas/liquid sampler for closed canister sampling in KW Basin. This document defines the tasks associated with the design, fabrication, assembly, and acceptance testing equipment necessary for gas and liquid sampling of the Mark I and Mark II canisters in the K-West basin. The sampling of the gas space and the remaining liquid inside the closed canisters will be used to help understand any changes to the fuel elements and the canisters. Specifically, this work plan will define the scope of work and required task structure, list the technical requirements, describe design configuration control and verification methodologies, detail quality assurance requirements, and present a baseline estimate and schedule.
Date: February 1, 1995
Creator: Pitkoff, C.C.
Partner: UNT Libraries Government Documents Department

Interface agreement for the management of FFTF Spent Nuclear Fuel

Description: The Hanford Site Spent Nuclear Fuel (SNF) Project was formed to manage the SNF at Hanford. The mission of the Fast Flux Test Facility (FFTF) Transition Project is to place the facility in a radiologically and industrially safe shutdown condition for turnover to the Environmental Restoration Contractor (ERC) for subsequent D&D. To satisfy both project missions, FFTF SNF must be removed from the FFTF and subsequently dispositioned. This documented provides the interface agreement between FFTF Transition Project and SNF Project for management of the FFTF SNF.
Date: February 2, 1995
Creator: McCormack, R.L.
Partner: UNT Libraries Government Documents Department

Evaluation of hyperbaric filtration for fine coal dewatering. Twelfth quarterly technical progress report, July 1, 1995--September 30, 1995

Description: The main objectives of the project are to investigate the fundamental aspects of particle-liquid interaction in fine coal dewatering, to conduct laboratory and pilot plant studies on the applicability of hyperbaric filter systems and to develop process conditions for dewatering of fine clean coal to less than 20 percent moisture. The program consist of three phases, namely: (1) Phase I Model Development; (2) Phase II Laboratory Studies; and (3) Phase III Field Testing. The Pennsylvania State University is leading efforts in Phase I, the University of Kentucky in Phase 11, and Consol Inc. in Phase III of the program. All three organizations are involved in all the three phases of the program. The Pennsylvania State University is developing a theoretical model for hyperbaric filtration systems, whereas the University of Kentucky is conducting experimental studies to investigate fundamental aspects of particle-liquid interaction and application of high pressure filter in fine coal dewatering. The optimum filtration conditions identified in Phase I and II will be tested in a Consol Inc. coal preparation plant using an Andritz Ruthner portable hyperbaric filtration unit.
Date: February 1, 1996
Creator: Parekh, B.K.; Hogg, R. & Fonseca, A.
Partner: UNT Libraries Government Documents Department

CSER 97-001 Criticality safety limits for PFP 26-inch vacuum lineremoval

Description: As part of the plutonium stabilization operations in the 234-5Z Building, several runs of 26-inch (26 inches of Hg) process vacuum header, along with associated smaller piping is to be cut into sections and disposed of. This criticality safety evaluation report (CSER) requested by Nirider (1996) addresses the removal of several hundred feet of abandoned 3 and 4 inch nominal diameter vacuum header and associated smaller diameter piping runs located in the duct level of the 234-5Z Building in rooms 262, 263, and 264 as shown in the two attached drawings.
Date: February 14, 1997
Creator: Himes, D. A.
Partner: UNT Libraries Government Documents Department

Modelling sorption of radionuclides on sorbent containing surface sites with variable charges: Ni-Sr-goethite system

Description: Results are presented on the retardation of radionuclides by sorption processes during host rock-ground water interactions. Studies are being performed at Yucca Mountain as part of a site selection for the underground disposal of high-level radioactive wastes. Tuff has a high sorption capacity for radionuclides. Several types of zeolites and montmorillonite, as well as goethite are known to occur in the tuff. Ion exchange phase equilibrium theory is used to describe sorption of mixtures of nickel and strontium ions in aqueous phase on goethite at a constant pH.
Date: February 1, 1996
Creator: Rao, M.G. & Halle, H.N.
Partner: UNT Libraries Government Documents Department

Ohmic contacts to Si-implanted and un-implanted n-type GaN

Description: We report on ohmic contacts to Si-implanted and un-implanted n-type GaN on sapphire. A ring shaped contact design avoids the need to isolate the contact structures by additional implantation or etching. Metal layers of Al and Ti/Al were investigated. On un-implanted GaN, post metalization annealing was performed in an RTA for 30 seconds in N{sub 2} at 700, 800, and 900 C. A minimum specific contact resistance (r{sub c}) of 1.4{times}10{sup -5} {Omega}{minus}cm{sup 2} was measured for Ti/Al at an annealing temperature of 800 C. Although these values are reasonably low, variations of 95% in specific contact resistance were measured within a 500 {mu}m distance on the wafer. These results are most likely caused by the presence of compensating hydrogen. Specific contact resistance variation was reduced from 95 to 10% by annealing at 900 C prior to metalization. On Si-implanted GaN, un-annealed ohmic contacts were formed with Ti/Al metalization. The implant activation anneal of 1120 C generates nitrogen vacancies that leave the surface heavily n-type, which makes un-annealed ohmic contacts with low contact resistivity possible.
Date: February 1996
Creator: Brown, J.; Ramer, J.; Zheng, L. F.; Hersee, S. D. & Zolper, J.
Partner: UNT Libraries Government Documents Department

Model documentation Natural Gas Transmission and Distribution Model of the National Energy Modeling System. Volume 1

Description: The Natural Gas Transmission and Distribution Model (NGTDM) of the National Energy Modeling System is developed and maintained by the Energy Information Administration (EIA), Office of Integrated Analysis and Forecasting. This report documents the archived version of the NGTDM that was used to produce the natural gas forecasts presented in the Annual Energy Outlook 1996, (DOE/EIA-0383(96)). The purpose of this report is to provide a reference document for model analysts, users, and the public that defines the objectives of the model, describes its basic approach, and provides detail on the methodology employed. Previously this report represented Volume I of a two-volume set. Volume II reported on model performance, detailing convergence criteria and properties, results of sensitivity testing, comparison of model outputs with the literature and/or other model results, and major unresolved issues.
Date: February 26, 1996
Partner: UNT Libraries Government Documents Department

Remediating the INEL`s buried mixed waste tanks

Description: The Idaho National Engineering Laboratory (INEL), formerly the National Reactor Testing Station (NRTS), encompasses 890 square miles and is located in southeast Idaho. In 1949, the United States Atomic Energy Commission, now the Department of Energy (DOE), established the NRTS as a site for the building and testing of nuclear facilities. Wastes generated during the building and testing of these nuclear facilities were disposed within the boundaries of the site. These mixed wastes, containing radionuclides and hazardous materials, were often stored in underground tanks for future disposal. The INEL has 11 buried mixed waste storage tanks regulated under the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) ranging in size from 400 to 50,000 gallons. These tanks are constructed of either stainless or carbon steel and are located at 3 distinct geographic locations across the INEL. These tanks have been grouped based on their similarities in an effort to save money and decrease the time required to complete the necessary remediation. Environmental Restoration and Technology Development personnel are teaming in an effort to address the remediation problem systematically.
Date: February 28, 1996
Creator: Kuhns, D.J.; Matthern, G.E. & Reese, C.L.
Partner: UNT Libraries Government Documents Department

Summary of field operations Tijeras Arroyo Well TJA-2. Site-Wide Hydrogeologic Characterization Project

Description: This report is a basic data report for field operations associated with the drilling, logging, completion, and development of Tijeras Arroyo well TJA-2. This test/monitoring well was installed as part of Sandia National Laboratories, New Mexico, Environmental Restoration Project.
Date: February 1, 1995
Creator: Foutz, W.L. & McCord, J.P.
Partner: UNT Libraries Government Documents Department

A case study in automated theorem proving: A difficult problem about commutators

Description: This paper shows how the automated deduction system OTTER. was used to prove the group theory theorem {chi}{sup 3} = e {implies} [[[y, z], u], v] = e, where e is the identity, and [XI Y] is the commutator {chi}{prime}y{prime}{chi}y. This is a difficult problem for automated provers, and several lengthy searches were run before a proof was found. Problem formulation and search strategy played a key role in the success. I believe that ours is the first automated proof of the theorem.
Date: February 1, 1995
Creator: McCune, W.
Partner: UNT Libraries Government Documents Department

Hanford Waste Vitrification Plant hydrogen generation study: Formation of ammonia from nitrate and nitrate in hydrogen generating systems

Description: The Hanford Waste Vitrification Plant (HWVP) is being designed for the Departrnent of Energy (DOE) to immobilize pretreated highly radioactive wastes in glass for permanent disposal in the HWVP, formic acid is added to the waste before vitrification to adjust glass redox and melter feed rheology. The operation of the glass melter and durability of the glass are affected by the glass oxidation state. Formation of a conductive metallic sludge in an over-reduced melt can result in a shortened melter lifetime. An over-oxidized melt may lead to foaming and loss of ruthenium as volatile RuO{sub 4}. Historically, foaming in the joule heated ceramic melter has been attributed to gas generation in the melt which is controlled by instruction of a reductant such as formic acid into the melter feed. Formic acid is also found to decrease the melter feed viscosity thereby facilitating pumping. This technical report discusses the noble metal catalyzed formic acid reduction of nitrite and/or nitrate to ammonia, a problem of considerable concern because of the generation of a potential ammonium nitrate explosion hazard in the plant ventilation system.
Date: February 1, 1996
Creator: King, R.B. & Bhattacharyya, N.K.
Partner: UNT Libraries Government Documents Department

Acceptance test report, 241-SY-101 Flexible Receiver System, Phase 3 testing

Description: This document summarizes the results of the phase 3 acceptance test of the 241-SY-101 Flexible Receiver System (FRS). The purpose of this acceptance test is to verify the sealing integrity of the FRS to ensure that the release of waste and aerosols will be minimized during the removal of the test mixer pump from Tank 241-SY-101. The FRS is one of six major components of the Equipment Removal System, which has been designed to retrieve, transport, and store the mixer pump. This acceptance test was performed at the 306E Facility in the 300 area from January 10, 1995 to January 17, 1995. The Phase 3 test consisted of two parts. Part one was a water leak test of the seal between the blast shield and mock load distribution frame (LDF) to ensure that significant contamination of the pump pit and waste interaction with the aluminum impact-limiting material under the LDF are prevented during the pump removal operation. The second part of this acceptance test was an air leak test of the assembled flexible receiver system. The purpose of this test was to verify that the release of hazardous aerosols will be minimized if the tank dome pressure becomes slightly positive during the decontamination of the mixer pump.
Date: February 6, 1995
Creator: Ritter, G.A.
Partner: UNT Libraries Government Documents Department