Annual report of the Texas Dairy Herd Improvement Association describing goals, activities, and accomplishments during fiscal year 1995.

A comprehensive report of the NTIEVA Advocacy Program, weaving together narratives of initiatives, triumphs, and strategic insights. Crafted exclusively for the Edward and Betty Marcus Foundation, the document paints a vivid picture of the program's profound influence on art education advocacy, showcasing a commitment to nurturing creativity and innovation in the educational landscape.

An insightful mentor review conducted by Nancy Walkup, providing a comprehensive assessment of the collaborative efforts and teaching practices within the sixth-grade team at Daggett Middle School.

A document outlining the North Texas Institute for Educators on the Visual Arts (NTIEVA) FY96 financial report. Sections are listed as follows: "Financial Report FY 96; July 1, 1995 - June 30, 1996"; "Comparison of Approved Budget of Center Funds to Actual Expenditures"; "Summary of Getty Funds/Cash Match Expenditures to Approved Budget"; "Cash Match Sources FY96"; and "Interest Income FY96."

This paper is a transcript of testimony by Alvin W. Trivelpiece, director of ORNL, before Congressional Subcommittee on Science, Technology, and Space. Dr. Trivelpiece discusses the importance of training scientist and engineers for the year 2000. (FSD)

The commissioning of the Tevatron was completed in 1983 and immediately, thereafter the experimental physics program began. The initial program involved using the Tevatron, first at 400GeV and then at 800GeV to supply beam for fixed target experiments. Beginning in 1985 the collider program has alternated with the fixed target program. The collider program runs with 900GeV protons and anti-protons. In the period since 1983, in addition to providing beam for the High Energy Physics program, we have had to shut down the Tevatron for modifications to the lattice (as dictated by the demands of the physics program) and for repairs to the magnets. These repairs have resulted in an accelerator that operates with high efficiency and reliability.

ASPEN computer simulation cases involving methanol, ethanol and propanol recycle have been completed. The results indicate that the yield of higher alcohols increased slightly until the quantity of recycled lower alcohol equaled the amount of that alcohol produced (i.e. when there is no net formation of the recycled alcohol). Above this point, no change in higher alcohol yield was observed. All cases were based on a 2/1 H{sub 2}/CO feed ratio at 70 atm and 275{degree}C. ASPEN PLUS simulations of the thermodynamics of higher alcohol synthesis were carried out based on non-ideal, equation-of-state models. The models used were the Peng-Robinson and the Redlich-Kwong-Aspen equations of state. The results of these simulations indicate very little difference between the results obtained with the ideal fluid model and the non-ideal models. No significant changes were found in reactant conversion, product distribution or product yield. All laboratory renovations are now complete.

Booklet describing the services provided by the Aircraft Pooling Board, with a memorandum that the weekly flights to Dallas are cancelled.

The light-duty utility arm (LDUA) is a seven-joint stainless steel robotic arm with a payload capacity of 75 lb. The robotic arm is deployed vertically with a maximum vertical reach of 63 ft. and a maximum horizontal reach of 13.5 ft. The functional requirements of the LDUA system are mapping and characterization of waste in Hanford single-shell tanks (SST) before and during waste retrieval. The LDUA system consists of a mobile deployment system (MDS), a vertical positioning mast (VPM), a tank riser interface confinement (TRIC), the LDUA, and a controller subsystem or support trailer. Currently, the system is in design and is subject to change; however, the LDUA or robotic arm will be deployed through a 12-in. riser above the tank dome. Field trips were performed to gather specifics for future deployment of the LDUA in Tank 241-A-105. The purpose of this report is to support two previous reports for the investigation of SSTs for deployment of the LDUA system. The first report identified the availability of risers while the second report identified the availability of Tanks 241-A-105, 241-A-S-109, 241-A-T-101, and 241-A-T-109 for deployment of the LDUA system. The second report also identified those 4- and 12-in. risers that could …

This is a note originally distributed in 1983. I am re-releasing it now, with a couple of words changed, so that it can be used for test problems, distributed more openly, and so forth. One could argue that it should be published, but I do not have time to reshape it into something I would regard as suitable for journal publication. A different derivation of the same result is being published in an appendix in D.W. Phillion and S.M. Pollaine, ``Dynamical Compensation of Irradiation Nonuniformities in a Spherical Hohlraum Illuminated with Tetrahedral Symmetry by Laser Beams,`` submitted to Phys. Plasmas.

The Waste Receiving and Processing (WRAP) Facility is being designed for construction in the north end of the Central Waste Complex. The WRAP Facility will receive, store, and process radioactive solid waste of both transuranic (TRU) and mixed waste (mixed radioactive-chemical waste) categories. Most of the waste is in 208-L (55-gal) steel drums. Other containers such as wood and steel boxes, and various sized drums will also be processed in the facility. The largest volume of waste and the type addressed in this report is TRU in 208-L (55-gal) drums that is scheduled to be processed in the Waste Receiving and Processing Facility Module 1 (WRAP 1). Half of the TRU waste processed by WRAP 1 is expected to be retrieved stored waste and the other half newly generated waste. Both the stored and new waste will be processed to certify it for permanent storage in the Waste Isolation Pilot Plant (WIPP) or disposal. The stored waste will go through a process of retrieval, examination, analysis, segregation, repackaging, relabeling, and documentation before certification and WIPP shipment. Newly generated waste should be much easier to process and certify. However, a substantial number of drums of both retrievable and newly generated waste …

We derive bounds on the mixing of the standard charge -1/3 quarks with vector-like isosinglet quarks, as they exist in some extensions of the standard model. We make no assumptions about the unitarity or any other features of the mixing matrix. We find that the mixing is quite constrained: we are able to set bounds on all the extra parameters which arise in the mixing matrix (CKM matrix), except on two phases. The assumption that there exists only one exotic quark leads to some extra relationships among the parameters of the mixing matrix.

The authors continue their investigation of {open_quotes}Crystalline Beams{close_quotes} in the ground state. In this paper they study the possibility of storing an intense beam of charged particles in a storage ring where the particles acquire a horizontal zigzag configuration. They define the equilibrium configuration, and examine the confinement and stability conditions. The problem of {open_quotes}shear{close_quotes} between particles circulating side by side caused by the curvature of the trajectories is examined and solved.

High Level Waste Programs has radioactive waste storage, treatment and processing facilities that are located in the F and H Areas at the Savannah River Site. These facilities include the Effluent Treatment Facility (ETF), F and H Area Tank Farms, Extended Sludge Processing (ESP), and In-Tank Precipitation (ITP). Job wastes are generated from operation, maintenance, and construction activities inside radiological areas. These items may have been contaminated with radioactive supernate, salt, and sludge material. Most of these wastes will be disposed of in the E-area Vaults. Therefore, an isotopic and hazardous characterization must be performed. The characterization of HLW supernate radionuclides is discussed in Chapter I. The characterization for salt and sludge phases, which can also contaminate LLW, will be included in other Chapters.

This report presents a summary of electric power industry statistics at national, regional, and state levels: generating capability and additions, net generation, fossil-fuel statistics, retail sales and revenue, finanical statistics, environmental statistics, power transactions, demand side management, nonutility power producers. Purpose is to provide industry decisionmakers, government policymakers, analysts, and the public with historical data that may be used in understanding US electricity markets.

The Liquid Effluent Monitoring Information System (LEMIS) is being developed as the organized information repository facility in support of the liquid effluent monitoring requirements of the Tri-Party Agreement. It is necessary to provide an automated repository into which the results from liquid effluent sampling will be placed. This repository must provide for effective retention, review, and retrieval of selected sample data by authorized persons and organizations. This System Architecture document is the aggregation of the DMR P+ methodology project management deliverables. Together they represent a description of the project and its plan through four Releases, corresponding to the definition and prioritization of requirements defined by the user.

Sodium-potassium alloy (NaK) is currently treated at the Y-12 Plant by open burning. Due to uncertainties with future permits for this process alternative treatment methods were investigated, revealing that two treatment processes are feasible. One process reacts the NaK with water in a highly concentrated molten caustic solution (sodium and potassium hydroxide). The final waste is a caustic that may be used elsewhere in the plant. This process has two safety concerns: Hot corrosive materials used throughout the process present handling difficulties and the process must be carefully controlled (temperature and water content) to avoid explosive NaK reactions. To avoid these problems a second process was developed that dissolves NaK in a mixture of propylene glycol and water at room temperature. While this process is safer, it generates more waste than the caustic process. The waste may possibly be used as a carbon food source in biological waste treatment operations at the Y-12 Plant. Experiments were conducted to demonstrate both processes, and they showed that both processes are feasible alternatives for NaK treatment. Process flow sheets with mass balances were generated for both processes and compared. While the caustic process generates less waste, the propylene glycol process is safer in …

A principal objective of this work was to study the conversion of coal to C{sub 2} {minus} C{sub 4} hydrocarbons in a two-stage reactor system. Coal was converted to liquids at 440{degrees}C in a stirred batch autoclave using tetralin as the hydrogen donor solvent. The liquids produced were separated from the unreacted coal and ash by filtration. The liquids were then fed into a second stage fixed bed reactor containing sulfided Ni-Mo/Al{sub 2}O{sub 3} and SiO{sub 2{minus}}Al{sub 2}O{sub 3} catalyst. The liquids were hydrocracked on the dual functional catalyst giving high yields of C{sub 2} {minus} C{sub 4}. hydrocarbons. The pressure was 1800 psi and the temperatures were in the range of 425 to 500{degrees}C. The kinetic parameters of the conversion of coal liquids to gases were determined. The activation energy was determined.

Forty-four sediment samples were collected from 28 locations in the Hanford Reach of the Columbia River to assess the presence of metals and man-made radionuclides in the near shore and shoreline settings of the Hanford Site. Three locations were sampled upriver of the Hanford Site plutonium production reactors. Twenty-two locations were sampled near the reactors. Three locations were sampled downstream of the reactors near the Hanford Townsite. Sediment was collected from depths of 0 to 6 in. and between 12 to 24 in. below the surface. Samples containing concentrations of metals exceeding the 95 % upper threshold limit values (DOE-RL 1993b) are considered contaminated. Contamination by arsenic, chromium, copper, lead, and zinc was found. Man-made radionuclides occur in all samples except four collected opposite the Hanford Townsite. Man-made radionuclide concentrations were generally less than 1 pCi/g.

The general objectives are to: (1) to identify and develop gelled polymer systems which have potential to improve reservoir conformance of fluid displacement processes, (2) to determine the performance of these systems in bulk and in porous media, and (3) to develop methods to predict the capability of these systems to recover oil from petroleum reservoirs. This work focuses on three types of gel systems--an aqueous polysaccharide (KUSP 1) system that gels as a function of pH, the chromium(III)-polyacrylamide system and the aluminum citrate-polyacrylamide system. Laboratory research is directed at the fundamental understanding of the physics and chemistry of the gelation process in bulk form and in porous media. This knowledge will be used to develop conceptual and mathematical models of the gelation process. Mathematical models will then be extended to predict the performance of gelled polymer treatments in oil reservoirs.

Test Engineering was supported by Tank Waste Remediation System Safety Programs Engineering Support in the performance of an Acceptance Test Procedure (ATP) to qualify the Standard Hydrogen Monitoring System (SHMS) cabinet installed on waste tank 241-SY-103. The June 7, 1994 ATP performance was controlled by West Waste Tank Farms work package 2W-94-322. The ATP was conducted following the final installation of a second Whittaker electro-chemical hydrogen monitoring cell. The cabinet had been sited on the waste tank two years earlier, but never connected to the exhaust vent header to monitor Tank 241-SY-103 vent header exhaust gases. The cabinet was then modified, to remove two undesirable solid state hydrogen monitors and install a second Whittaker electro-chemical hydrogen monitoring sensor and signal conditioning. The ATP was used to assure that the cabinet wiring and components were properly installed and labeled and that the two years without operation had not seriously damaged the installed equipment. Electrical and pneumatic tests were performed to assure system integrity.

Previous segregation and repackaging operations involving removal of N-fuel elements resulted in fuel elements being stuck and unable to be removed from their canisters. This workplan describes the methods of development for slitting the walls of the three different types of canisters. Slitting the canister walls will allow the canister to expand and permit any stuck fuel elements to be removed from the canister. The Engineering Testing Laboratory (ETL) will develop and test a prototype canister slitter; evaluate existing slitter for usage or re-design; develop fabrication and assembly drawings; provide design calculations as required; and fabricate the canister slitter.

A stack of lead and scintillator was placed in a neutral beam obtained from targeting 800 GeV protons. Small pieces of film containing radiochromic dye were placed adjacent to the layers of scintillator for the purpose of measuring the radiation dose to the scintillator. Our motivation was to calibrate the radiation dose obtainable in this manner for future tests of scintillator for SSC experiments and to relate dose to flux to check absolute normalization for calculations. We also observed several other radiation effects which should be considered for both damage and compensation in a calorimeter.

Several equations have been proposed in the literature to describe the variation of resistivity with temperature {rho}(T), for the superconducting oxides. Among these, a linear variation of {rho}(T) has been accepted as a characteristic feature for these materials. These equations have been compared through least squares to experimental values of {rho}(T) for one case of YBa{sub 2}Cu{sub 3}O{sub 7{minus}{delta}} with {delta} near 0.1. It has been found that two equations, (a) one based on an averaged density of state and small Fermi and thermal gap energies and (b) another based on Holstein`s small polaron, yield the lowest percent deviations from the experimental values and the smallest chi squared/degree of freedom. They are also the only equations that describe quantitatively the variations with both temperature and composition.