The objective of this activity is to show that the use of the traditional strength of materials approach to the drip shield and the waste package (WP) designs is bounding and appropriate when compared to the fracture mechanics approach. The scope of this activity is limited to determining the failure assessment diagrams for the two materials at issue: Ti-7 and Alloy 22. This calculation is intended for use in support of the license application design of the drip shield and the WP. This activity is associated with the drip shield and the WP designs. The activity evaluation for work package number P32 12234F2, included in ''Technical Work Plan for: Waste Package Design Description for LA'', has determined that the development of this document is subject to ''Quality Assurance Requirements and Description'' requirements. The control of the electronic management of data is accomplished in accordance with the methods specified in Reference 1, Section 10. AP-3.124, ''Design Calculations and Analysis'' (Ref. 2), is used to develop and document the calculation.

Annual report of the U.S. Global Change Research Program documenting activities and progress, goals for the upcoming year, proposed budget considerations, and other information about the organization for fiscal year 2000.

This report provides information on the timing of submission of the mid-session review for FY1980-FY2009, a 30-year period that covers all or part of the administrations of five Presidents, applying to the last two years of the Carter Administration, and the full terms of the Reagan, George H. W. Bush, Clinton, and George W. Bush Administrations.

The purpose of this report is to help understand how the budget increases of the last ten years have been allocated.

Palladium used at Savannah River (SR) for process tritium storage is currently obtained from a commercial source. In order to understand the processes involved in preparing this material, SR is supporting investigations into the chemical reactions used to synthesize this material. The material specifications are shown in Table 1. An improved understanding of the chemical processes should help to guarantee a continued reliable source of Pd in the future. As part of this evaluation, a work-for-others contract between Westinghouse Savannah River Company and Ames Laboratory (AL) was initiated. During FY98, the process for producing Pd powder developed in 1986 by Dan Grove of Mound Applied Technologies, USDOE (the Mound muddy water process) was studied to understand the processing conditions that lead to changes in morphology in the final product. During FY99 and FY00, the process for producing Pd powder that has been used previously at Sandia and Los Alamos National Laboratories (the Sandia/LANL process) was studied to understand the processing conditions that lead to changes in the morphology of the final Pd product. During FY01, scale-up of the process to batch sizes greater than 600 grams of Pd using a 20-gallon Pfaudler reactor was conducted by the Iowa State University …

This report discusses funding and policy issues regarding the Food and Drug Administration (FDA), which is responsible for ensuring the safety of foods, drugs, medical devices, cosmetics, and other products.

Financial report for the University of North Texas Health Science Center contains information about revenues and expenditures for the organization during the 1999-2000 fiscal year. It includes general statements, schedules of accounts broken down by category, and other supplementary notes.

Financial report for the University of North Texas System (including the UNT Denton, Texas campus and the UNT Health Science Center in Fort Worth, Texas) contains information about revenues and expenditures for the organization during the 1999-2000 fiscal year. It includes general statements, schedules of accounts broken down by category, and other supplementary notes.

Financial report for the University of North Texas in Denton, Texas contains information about revenues and expenditures for the organization during the 1999-2000 fiscal year. It includes general statements, schedules of accounts broken down by category, and other supplementary notes.

In accordance with EM's office of Science and Technology (OST), the TFA is committed to assessing the maturity of technology development projects and ensuring their readiness for implementation and subsequent deployment. The TFA conducts an annual Midyear Review to document the status of ongoing projects, reaffirm and document user commitment to selected projects, and to improve the effective deployment of technology by determining and documenting the readiness of selected projects to move ahead. Since 1995, OST has used a linear technology maturation model that spans through seven defined stages of maturity, from basic research to implementation. Application of this Stage/Gate model to technology development resulted in prescriptive and somewhat cumbersome review procedures, resulting in limited and inconsistent use. Subsequently, in February 2000, OST issued revised guidance in an effort to streamline the technology tracking and review process. While the new OST guidance reinforces peer review requirements and the use of the American Society of Mechanical Engineers (ASME) for independent reviews, it also implements a simplified Gate model. The TFA is now responsible for providing auditable documentation for passing only three stages of technology maturity: ready for research (Gate 0); ready for development (Gate 2); ready for demonstration (Gate 5). The …

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A major milestone was reached in Fiscal Year (FY) 2000--the completion of the Chicago Pile-5 (CP-5) D and D Project. CP-5, the first reactor built on the Argonne National Laboratory-East (ANL-E) site, was a 5-megawatt, heavy water-moderated, enriched uranium-fueled reactor. It was the principal reactor on the Argonne site used to produce neutrons for scientific research from 1954 to 1979. The reactor was shut down and defueled in 1979, and placed in a lay-up condition. In 1990, funding was provided to begin the decontamination and decommissioning (D and D) of this facility, and work began in June 1991. D and D tasks were performed by both ANL-E personnel and subcontractor personnel from Duke Engineering and Services, Marlborough MA, under the management of ANL-E D and D Program personnel. In July 2000, the final project report was presented to the Department of Energy, and the facility was formally decommissioned and transferred to the landlord. Total project duration was 97 months, and total project cost was $29.5M. Also, in FY 2000, work began on the 60 Cyclotron D and D Project. An accelerator used for basic research, this facility produced beams of deuterons, helium ions, singly charged hydrogen molecules, and neutrons of …

In August 1995, the United States took a significant step to reduce the nuclear danger. The decision to pursue a zero- yield Comprehensive Test Ban Treaty will allow greater control over the proliferation of nuclear weapons and will halt the growth of new nuclear systems. This step is only possible because of the Stockpile Stewardship Program, which provides an alternative means of ensuring the safety, performance, and reliability of the United States' enduring stockpile. At the heart of the Stockpile Stewardship Program is ASCI, which will create the high-confidence simulation capabilities needed to integrate fundamental science, experiments, and archival data into the stewardship of the actual weapons in the stockpile. ASCI will also serve to drive the development of simulation as a national resource by working closely with the computer industry and with universities.

This report contains the program plan and background information for the Heavy Vehicle Hybrid Propulsion R and D Program sponsored by the Department of Energy's Office of Heavy Vehicle Technologies. The program is a collaboration between industry and government established for the development of advanced hybrid-electric propulsion technology for urban cycle trucks and buses. It targets specific applications to enhance potential market success. Potential end-users are also involved.

The fabrication of boron-covered crystal scintillation detectors is described. Bulk boron-loaded epoxy material was cast and cut into 0.5 mm-thick wafers that were mounted on CdWO{sub 4} and CsI(Tl) crystals. The crystals were mounted on miniature photomultiplier tubes and gamma spectra were obtained with the detectors. The ability of these small detectors to produce spectra that can be analyzed to provide isotopic identification has been demonstrated. In addition, the detector can produce a signature indicating the presence of neutrons. The same miniature size of these detectors that makes them attractive for hand-held portable use, may be a limiting factor in their efficiency. The small size of the scintillation crystals makes them not as efficient as larger NaI(Tl) crystals simply by virtue of significantly decreased sensitive volume and surface area. It may be worthwhile to consider slightly larger crystals (approximately 15 mm cubic CdWO{sub 4}) mounted on rectangular photomultipliers in a detecting head connected to the electronics package by a signal cable.

This is the FY00 Annual Progress report for the Laboratory Directed Research and Development (LDRD) Program at Los Alamos National Laboratory. It gives an overview of the LDRD Program, summarizes progress on each project conducted during FY00, characterizes the projects according to their relevance to major funding sources, and provides an index to principal investigators. Project summaries are grouped by LDRD component: Directed Research and Exploratory Research. Within each component, they are further grouped into the ten technical categories: (1) atomic, molecular, optical, and plasma physics, fluids, and beams, (2) bioscience, (3) chemistry, (4) computer science and software engineering, (5) engineering science, (6) geoscience, space science, and astrophysics, (7) instrumentation and diagnostics, (8) materials science, (9) mathematics, simulation, and modeling, and (10) nuclear and particle physics.

The Low-Activity Waste Process Technology Program anticipated that grouting will be used for disposal of low-level and transuranic wastes generated at the Idaho Nuclear Technology Engineering Center (INTEC). During fiscal year 2000, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed using silica gel and other absorbents to solidify sodium-bearing wastes. A feasibility study and conceptual design were completed for the construction of a grout pilot plant for simulated wastes and demonstration facility for actual wastes.

The fabrication of boron-covered crystal scintillation detectors is described. Bulk boron-loaded epoxy material was cast and cut into 0.5 mm-thick wafers that were mounted on CdWO{sub 4} and CsI(Tl) crystals. The crystals were mounted on miniature photomultiplier tubes and gamma spectra were obtained with the detectors. The ability of these small detectors to produce spectra that can be analyzed to provide isotopic identification has been demonstrated. In addition, the detector can produce a signature indicating the presence of neutrons. The same miniature size of these detectors that makes them attractive for hand-held portable use, may be a limiting factor in their efficiency. The small size of the scintillation crystals makes them not as efficient as larger NaI(Tl) crystals simply by virtue of significantly decreased sensitive volume and surface area. It may be worthwhile to consider slightly larger crystals (approximately 15 mm cubic CdWO{sub 4}) mounted on rectangular photomultipliers in a detecting head connected to the electronics package by a signal cable.

Most large-scale high-critical-temperature superconductor applications require wires or tapes that an carry high currents in applied magnetic fields. This report describes technical progress of research and development efforts aimed at producing superconducting components and devices in the Y-Ba-Cu-O and Bi-(Pb)-Sr-Ca-Cu-O systems. Topics discussed are formation of first- and second-generation composite conductors, characterization of structures and superconducting and mechanical properties, modeling of grain-boundary current transport, and fabrication and analysis of prototype components.

This self-evaluation report offers a summary of results from FY2000 actions to achieve Pacific Northwest National Laboratory's strategy and provides an analysis of the state of their self-assessment process. The result of their integrated planning and assessment process identifies Laboratory strengths and opportunities for improvement. Critical elements of that process are included in this report; namely, a high-level summary of external oversight activities, progress against Operations Improvement Initiatives, and a summary of Laboratory strengths and areas for improvement developed by management from across the laboratory. Some key areas targeted for improvement in FY2001 are: systems approach to resource management; information protection; integrated safety management flow-down to the benchtop; cost management; integrated assessment; Price Anderson Amendments Act (PAAA) Program; and travel risk mitigation.

Problems with pipeline plugs at Hanford have occurred throughout its tank farm system. Most cross-site transfer lines at Hanford are no longer functional due to these plugs. Waste transfers frequently led to partial line plugs, resulting in substantial amounts of water being added to the tank system in an attempt to free the lines. In response to these plugs, the Hanford tank farm developed waste acceptance criteria that a waste must pass before it can be transferred (Shekarriz et al., 1997). The criteria, which include physical properties such as viscosity, specific gravity, and percent solids, are based primarily on past operational experience. Unfortunately, the chemistry of the waste solutions was not included in the criteria even though the tank farm operators are fully aware of its importance. Pipeline plugs have also occurred during relatively short waste transfers at Hanford. In FY 2000, the effort to saltwell pump 50,000 gal of filtered waste from tank U-103 to tank SY-102 was delayed for several weeks due to a plugged pipeline. Attempts to locate the plug(s) determined that it had occurred in the 02-A flex and that other plugs were possible in each of the SY-farm flexes. Modifications such as larger flex jumpers …

This report documents the process used by the Tanks Focus Area (TFA) to analyze and develop responses to technology needs submitted by five major U.S. Department of Energy (DOE) sites with radioactive tank waste problems, and the initial results of the analysis. The sites are the Hanford Site, Idaho National Engineering and Environmental Laboratory (INEEL), Oak Ridge Reservation (ORR), Savannah River Site (SRS), and West Valley Demonstration Project (WVDP). During the past year, the TFA established a link with DOE's Fernald site to exchange, on a continuing basis, mutually beneficial technical information and assistance.

The Wastewater Triad Project (WTP) consists of three operational units: the cesium removal (CsR) system, the out-of-tank evaporator (OTE) system, and the solid/liquid separation (SLS) system. These systems were designed to reduce the volume and radioactivity of low-level liquid waste (LLLW) stored in the Melton Valley Storage Tanks (MVSTs) and are operated independently or in series in order to accomplish the treatment goals. Each is a modular, skid-mounted system that is self-contained, individually shielded, and designed to be decontaminated and removed once the project has been completed. The CsR and OTE systems are installed inside Building 7877; the SLS system is installed adjacent to the east side of the MVST 7830 vault cover. The CsR, which consists of ion-exchange equipment for removing {sup 137}Cs from LLLW, was demonstrated in 1997. During the Cesium Removal Demonstration, 30,853 gal of radioactive supernate was processed and 1142 Ci of {sup 137}Cs was removed from the supernate and loaded onto 70 gal of a crystalline silicotitanate sorbent manufactured by UOP, Inc. The OTE system is a subatmospheric single-stage evaporator system designed to concentrate LLLW to smaller volumes. It was previously demonstrated in 1996 and was operated in 1998 to process about 80,000 gal of …

This document reports the low-level radioactive waste, mixed low-level radioactive waste, and Polychlorinated Biphenyl contaminated low-level waste transported to or from the Nevada Test Site during fiscal year 2000.