Annual report for the superconductor program at Argonne National Laboratory discussing the group's activities and research. This report describes technical progress of research and development efforts aimed at producing superconducting components in the Y-Ba-Cu, (Bi,Pb)-Sr-Ca-Cu, (Tl,Pb,Bi)-(Ba,Sr)-Ca-Cu, and Hg-Ba-Ca-Cu-O oxide systems including: synthesis and heat treatment of high-Ta superconductors, formation of monolithic and composite conductors, characterization of structures and superconducting and mechanical properties, and fabrication and testing of prototype components.

In 1992, the mission of the Idaho Chemical Processing Plant was changed from reprocessing of spent nuclear fuels to development of technologies for conditioning of spent nuclear fuels and other high-level wastes for disposal in a geologic repository. In addition, the Department of Energy (DOE) directed Idaho National Engineering Laboratory (INEL) to develop a program plan addressing the management of radioactive contaminated scrap metal (RSM) within the DOE complex. Based on discussions with the EM-30 organization, the INEL Metal Recycle program plan was developed to address all issues of RSM management. Major options considered for RSM management were engineered interim storage, land disposal as low-level waste, and beneficial reuse/recycle. From its inception, the Metal Recycle program has emphasized avoidance of storage and disposal costs through beneficial reuse of RSM. The Metal Recycle program plan includes three major activities: Site-by-site inventory of RSM resources; validation of technologies for conversion of RSM to usable products; and identification of parties prepared to participate in development of a RSM recycle business.

Calcine dissolution studies were performed in FY-94,95 in order to extend the knowledge of dissolution and to obtain information necessary for scale-up design and operation. Experiments reported in this document were performed with non-radioactive and actual calcines to generate qualitative data regarding: (a) calcine dissolution rates, (b) undissolved solids settling characteristics, (c) undissolved solids heel formation, and (d) chemical treatments for undissolved solids heel dissolution. The goal of this work was to achieve complete calcine dissolution, or to determine conditions that would result in the maximum calcine dissolution. Small scale laboratory experiments (test-tube dissolutions) and a bench scale dissolver set-up were used in the effort. Results from this work show the bulk of the undissolved solids to settle at a rate of >9 inches per second when the baseline dissolution parameters are used. Baseline dissolution parameters were 100 grams of calcine being dissolved in 1 L of 5 M HNO{sub 3} at > 90 C while the solution is being vigorously and constantly mixed. This work also verified that dissolution is most complete when performed with aggressive mixing. Sequential dissolutions performed with non-radioactive and actual calcine indicate that little undissolved solids heel build-up is expected, and this small heel can …

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Sandia National Laboratories, New Mexico, conducts the Utility Battery Storage Systems Program, which is sponsored by the US Department of Energy`s Office of Energy Management. The goal of this program is to assist industry in developing cost-effective battery systems as a utility resource option by 2000. Sandia is responsible for the engineering analyses, contracted development, and testing of rechargeable batteries and systems for utility energy storage applications. This report details the technical achievements realized during fiscal year 1994.

This report describes the first practical, non-invasive technique for detecting and imaging currents internal to operating integrated circuits (ICs). This technique is based on magnetic force microscopy and was developed under Sandia National Laboratories` LDRD (Laboratory Directed Research and Development) program during FY 93 and FY 94. LDRD funds were also used to explore a related technique, charge force microscopy, for voltage probing of ICs. This report describes the technical work performed under this LDRD as well as the outcomes of the project in terms of publications and awards, intellectual property and licensing, synergistic work, potential future work, hiring of additional permanent staff, and benefits to DOE`s defense programs (DP).

The authors have been developing a novel threshold Cherenkov detector, consisting of a gas radiator followed by a UV photosensitive wire chamber using CsI photocathodes. The photo-detector lies directly in the particle path and is thus required to have single photo-electron sensitivity and yet to be insensitive to the passage of a charged particle. In addition, the detector should be made of low mass material to minimize the effect of multiple scatterings. The proposed threshold Cherenkov counters are called Hadron Blind Detectors (HBDs) because they are blind to low energy hadrons which have lower speed {beta} for given momentum p than that of electrons. HBDs can be used in colliders, especially heavy ion hadron colliders (RHIC, LHC), which have huge {number_sign} of hadrons produced per event, to select electrons by being blind to low-momentum hadrons. The authors have studied two different methods to build HBDs described as follows: (1) windowless configuration; (2) thin window configuration. The authors describe herewith their recent experimental results on HBD research obtained with CsI photo-cathodes and HBD prototype beam testing in 1995.

This report includes a brief analysis of federal research and development funding trends for the past six years as well as R&D funding projects to FY2000.

Annual report of the Edwards Underground Water District describing goals, activities, and accomplishments during fiscal year 1993-1994.

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The purpose of these experiments was to study the dissolution, retention, volatilization, and trapping of transuranic radionuclide elements (TRUs), mixed fission and activation products, and high vapor pressure metals (HVPMS) during processing in a high temperature arc furnace. In all cases, surrogate elements (lanthanides) were used in place of radioactive ones. The experiments were conducted utilizing a small DC arc melter developed at the Idaho National Engineering Laboratory (INEL) Research Center (IRC). The small arc melter was originally developed in 1992 and has been used previously for waste form studies of iron enriched basalt (IEB) and IEB with zirconium and titanium additions (IEB4). Section 3 contains a description of the small arc melter and its operational capabilities are discussed in Chapter 4. The remainder of the document describes each testing program and then discusses results and findings.

This study was conducted to evaluate the suitability of various locations for a new potable ground water well at Test Area North (TAN). The new well is proposed to replace two existing wells located within a trichloroethylene (TCE) plume. Several locations were evaluated using computer simulations based on the hydrogeology of the site. The modeling effort involved: (1) producing a water table map, (2) superimposing the effects of pumping the proposed new production well on the water table map using the model CAPZONE, and (3) calculating the capture zone for these wells using the GWPATH model. A three dimensional contaminant transport model was used to evaluate siting a well in a deeper horizon of the aquifer. The following scenarios were investigated: (1) placing a new well 500 ft north of the existing wells; (2) locating a well 3,000 ft northwest of the existing wells; (3) deepening one of the existing wells 100 to 150 ft to produce water from beneath an interbed that acts as a hydraulic barrier; and (4) drilling a new well about 500 ft northwest of the existing wells to produce water from beneath the interbed. The recommended new well site (fourth scenario) is northwest of the …

This report provides a synopsis of the budget activity related to AIDS from the discovery of the disease in 1981 through FY1999. Funding for AIDS research, prevention and treatment programs within the Department of Health and Human Services (HHS) discretionary budget has increased from $200,000 in FY1981 to an estimated $3.85 billion in FY1999.

Annual report of Lee College describing goals, activities, and accomplishments during fiscal year 1994-95 and 1995-96.

The report provides a synopsis of the FY94/95 Thermal Stabilization Campaign. The FY94 Thermal Stabilization Campaign ran from November 1, 1994 to June 13, 1995 and stabilized 236 items (22 kg) of reactive plutonium bearing material. A total of 49 cans of stabilized material was moved to the vaults for interim storage. While the initial downtime was high, with an Operating Efficiency (OE) of 27% over the first 3 months, the OE improved to 78% during the last 5 months for an overall DE of 58%. The campaign was completed 85 days ahead of schedule thus exceeding the ``Excellent``date for the Performance Base Incentive (PBI) for this campaign by 25 business days.

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The Cryocycling of Energetic Materials Project is sponsored by the Memorandum of Understanding (MOU) on advanced munition technologies. This MOU is an agreement between the Department of Energy and the Department of Defense (Office of Munitions) that facilitates the development of technologies of mutual interest to the two Departments. The cryocycling project is one of several that focus on demilitarization aspects of conventional weapons and weapon systems. During FY94 the project pursued the development of analytical and numerical models that can be used to describe and optimize the cryocycling process for preparing energetic materials for recycle and reuse. In addition, the demilitarization stockpile of the Department of Defense was analyzed to identify candidate munitions for the process, and pilot scale cryocycling operations were begun at an industrial contractor. When a material is cryocycled, it is repeatedly subjected to cycles of rapid cooling in a liquid nitrogen bath at 77 K followed by warming to ambient temperature. In laboratory and pilot scale demonstrations, the authors have shown that cryocycling can dramatically reduce the size of a variety of propellant grains and a number of cast and plastic bonded explosives.

This report presents the results of ambient air monitoring performed during the 1994 fiscal year (FY 1994) in the vicinity of McMurdo Station, Antarctica. Routine monitoring was performed during the 1993-1994 austral summer at three locations for airborne particulate matter less than 10 micrometers (PM-10) and at two locations for carbon monoxide (CO), sulfur dioxide (SO{sub 2}), and nitrogen oxides (NO, NO{sub 2}, and NO{sub x}). Selected PM-10 filters were analyzed for arsenic, beryllium, cadmium, chromium, lead, mercury, and nickel. Additional air samples were collected at three McMurdo area locations and at Black Island for determination of the airborne concentration of polychlorinated dibenzo-p-dioxins (PCDDs) and polychlorinated dibenzofurans (PCDFs). Sampling site selection, sampling procedures, and quality assurance procedures used were consistent with US Environmental Protection Agency guidance for local ambient air quality networks.

The goals of this project are to collect data that will assist in determining what constitutes a representative groundwater sample in fractured shale typical of much of the geology underlying the ORR waste disposal sites, and to determine how monitoring-well construction and sampling methods impact the representativeness of the sample. This report details the FY94 field activities at a research site in west Bear Creek Valley on the Oak Ridge Reservation (ORR). These activities funded by the Energy Systems Groundwater Program Office through the Oak Ridge Reservation Hydrologic and Geologic Studies (ORRHAGS) task, focus on developing appropriate sampling protocols for the type of fractured media that underlies many of the ORR waste disposal sites. Currently accepted protocols were developed for porous media and are likely to result in nonrepresentative samples in fractured systems.

Chapter III of the US Department of Energy (DOE) Order 5820.2A (DOE 1988) specifies requirements for the management of facilities that were used for the disposal of radioactive solid low-level waste (LLW) on or after the date of the order (September 26, 1988). Activities in Solid Waste Storage Area (SWSA) 6 at Oak Ridge National Laboratory (ORNL) are governed by Chapter III. Chapter II of 5820.2A covers the transuranic (TRU) waste storage areas in SWSA 5 North at ORNL. Both chapters require environmental monitoring to provide early warning of leaks before such leaks pose a threat to human health or the environment. Chapter III also requires the monitoring of LLW disposal facilities so that their performance can be evaluated. In order to comply with this Order, the Environmental Sciences Division (ESD) at ORNL implements the Active Sites Environmental Monitoring Program (ASEMP) for the Radioactive Solid Waste Operations (RSWO) Department within the Waste Management and Remedial Action Division (WMRAD) at ORNL. The scope of the ASEMP includes all ORNL waste disposal sites that were active on or after the date of the Order and that are under the operational control of the RSWO Department of WMRAD. This report continues a series …

A document outlining the North Texas Institute for Educators on the Visual Arts (NTIEVA) FY94 financial report. Sections are listed as follows: "Financial Report FY 94; July 1, 1993 - June 30, 1994"; "Comparison of Approved Budget of Center Funds to Actual Expenditures"; "FY94 Summary of Getty Funds/Cash Match Expenditures to Approved Budget"; "Cash Match Sources FY94"; and "Interest Income FY94."

A seven-page report to the Sunset Review Committee on the North Texas Institute for Educators on the Visual Arts (NTIEVA). Includes the history, goals, accomplishments, programs, and proposed plans for the institute, as well as a financial report.

This document contains six reports on actinide chemistry research supporting the Waste Isolation Pilot Plant (WIPP). These reports, completed in FY94, are relevant to the estimation of the potential dissolved actinide concentrations in WIPP brines under repository breach scenarios. Estimates of potential dissolved actinide concentrations are necessary for WIPP performance assessment calculations. The specific topics covered within this document are: the complexation of oxalate with Th(IV) and U(VI); the stability of Pu(VI) in one WIPP-specific brine environment both with and without carbonate present; the solubility of Nd(III) in a WIPP Salado brine surrogate as a function of hydrogen ion concentration; the steady-state dissolved plutonium concentrations in a synthetic WIPP Culebra brine surrogate; the development of a model for Nd(III) solubility and speciation in dilute to concentrated sodium carbonate and sodium bicarbonate solutions; and the development of a model for Np(V) solubility and speciation in dilute to concentrated sodium Perchlorate, sodium carbonate, and sodium chloride media.

This report lists all published documents of the Photovoltaic Program for FY 1994. Documents include conference papers, journal articles, book chapters, patents, etc.