This report presents the 2008 groundwater monitoring results collected by the U.S. Department of Energy (DOE) Office of Legacy Management (LM) for the Central Nevada Test Area (CNTA) Subsurface Corrective Action Unit (CAU) 443. Responsibility for the environmental site restoration of the CNTA was transferred from the DOE Office of Environmental Management (DOE-EM) to DOE-LM on October 1, 2006. The environmental restoration process and corrective action strategy for CAU 443 are conducted in accordance with the Federal Facility Agreement and Consent Order (FFACO 2005) entered into by DOE, the U.S. Department of Defense, and the State of Nevada. The corrective action strategy for the site includes proof-of-concept monitoring in support of site closure. This report summarizes investigation activities associated with CAU 443 that were conducted at the site during fiscal year 2008. This is the second groundwater monitoring report prepared by DOE-LM for the CNTA.

This report presents the 2008 groundwater monitoring results collected by the U.S. Department of Energy (DOE) Office of Legacy Management (LM) at the Project Shoal Area (PSA) Subsurface Corrective Action Unit (CAU) 447 located in Churchill County, Nevada. Responsibility for the environmental site restoration of the PSA was transferred from the DOE Office of Environmental Management to LM on October 1, 2006. The environmental restoration process and corrective action strategy for CAU 447 are conducted in accordance with the Federal Facility Agreement and Consent Order (FFACO 1996, as amended February 2008) entered into by DOE, the U.S. Department of Defense, and the State of Nevada. The corrective action strategy for the site includes proof of concept monitoring in support of site closure. This report summarizes investigation activities associated with CAU 447 that were conducted at the site during 2008. This is the second groundwater monitoring report prepared by LM for the PSA

This contains abstracts from the 2009 Annual Environmental Remediation Sciences Program (ERSP) Principal Investigators (PI) Meeting. The ERSP seeks to advance fundamental science to understand, predict, and mitigate the impacts of environmental contamination from past nuclear weapons production and provide a scientific basis for the long-term stewardship of nuclear waste disposal. These ambitious goals cannot be achieved by any one project alone. Therefore, ERSP funds a combination of research programs at the DOE national laboratories, individual projects at universities and federal agencies, and large long(er)-term field site research. Integration of these activities to advance the ERSP goals is a constant challenge, but made significantly simpler by bringing together all funded ERSP researchers once a year to discuss the very latest research results. It is at these meetings where new ideas and/or scientific advancements in support of ERSP goals can be discussed and openly debated among all PIs in the program. The ERSP thrives, in part, on the new ideas, concepts, scientific connections, and collaborations generated as a result of these meetings. The annual PI Meeting is very much a working meeting with three major goals: (1) to provide opportunities for scientific interaction among the ERSP scientists, a critical element for …

Fact sheet describes the top accomplishments, goals and strategies of DOEs Advanced Combustion Engine Research and Development sub program.

Algorithmic properties of the midpoint predictor-corrector time integration algorithm are examined. In the case of a finite number of iterations, the errors in angular momentum conservation and incremental objectivity are controlled by the number of iterations performed. Exact angular momentum conservation and exact incremental objectivity are achieved in the limit of an infinite number of iterations. A complete stability and dispersion analysis of the linearized algorithm is detailed. The main observation is that stability depends critically on the number of iterations performed.

The development of a set of safety codes and standards for hydrogen facilities is necessary to ensure they are designed and operated safely. To help ensure that a hydrogen facility meets an acceptable level of risk, code and standard development organizations are tilizing risk-informed concepts in developing hydrogen codes and standards.

The Annual Energy Outlook 2009 (AEO2009), prepared by the Energy Information Administration (EIA), presents long-term projections of energy supply, demand, and prices through 2030, based on results from EIA’s National Energy Modeling System (NEMS). EIA published an “early release” version of the AEO2009 reference case in December 2008.

Chloride stress corrosion cracking (SCC) is a plausible corrosion mechanism for the stainless steel 3013 containers during their lifetime for plutonium material storage if sufficient electrolyte is present within the container. Contributing factors for SCC, such as fabrication and welding residual stresses, are present in the 3013 cans. Convenience and inner cans from both Hanford and SRS are made by a flow form process, which cold works the stainless steel during fabrication. Additionally, the inner cans also are sealed at the can top with a closure weld to the sealing plug. Only SRS and Hanford were tested since moisture levels were significant for SCC. As part of the 3013 corrosion plan for FY09, testing in a boiling magnesium chloride solution was performed on actual 3013 convenience and inner cans to determine if the residual stresses were sufficient for the initiation and propagation of SCC. Additional testing in a 40% calcium chloride solution was also performed on 304L stainless steel SCC coupons, i.e. stressed teardrop-shaped samples (teardrops), and an inner can welded top to provide comparative results and to assess the effect of residual stresses in a less aggressive environment. The testing performed under this task consisted of 3013 inner and …

Various sources of risk exist for all civil structures, one of which is seismic risk. As structures change in scale, the magnitude of seismic risk changes relative to risk from other sources. This paper presents an introduction to seismic hazard as applied to wind turbine structures. The existing design methods and research regarding seismic risk for wind turbines is then summarized. Finally a preliminary assessment is made based on current guidelines to understand how tower moment demand scales as rated power increases. Potential areas of uncertainty in the application of the current guidelines are summarized.

Report of the Texas State Auditor's Office related to the sources of border security funding, the amounts spent in each category of expenditures for fiscal years 2004 through 2008 (including expenditures for staff, capital budget purchases, and information technology), and whether or not these expenditures were allocated appropriately.

Report of the Texas State Auditor's Office related to analysis of staffing levels and caseloads at the Department of Family and Protective Services to compare the results and evaluate the effectiveness of staffing strategies and enhancements over time, and verifying whether current caseload-per-worker performance measures, definitions, and methodologies accurately reflect the workloads of protective services caseworkers.

Report of the Texas State Auditor's Office related to examining the transactions of the Texas State University System Foundation's (Foundation) financing of the Texas Hall dormitory at Angelo State University, including the transactions involving the formation and dissolution of the limited liability company; and determining whether the Foundation has transferred all funds pertaining to the construction and operation of the Texan Hall dormitory appropriated, dedicated, or held for the use and benefit of Angelo State University to the Texas Tech University System.

The newly completed Idaho National Laboratory (INL) Carbon Characterization Laboratory (CCL) is located in Lab-C20 of the Idaho National Laboratory Research Center. This laboratory was established under the Next Generation Nuclear Plant (NGNP) Project to support graphite research and development activities. The CCL is designed to characterize and test carbon-based materials such as graphite, carbon-carbon composites, and silicon-carbide composite materials. The laboratory is fully prepared to measure material properties for nonirradiated carbon-based materials. Plans to establish the laboratory as a radiological facility within the next year are definitive. This laboratory will be modified to accommodate irradiated materials, after which it can be used to perform material property measurements on both irradiated and nonirradiated carbon-based material. Instruments, fixtures, and methods are in place for preirradiation measurements of bulk density, thermal diffusivity, coefficient of thermal expansion, elastic modulus, Young’s modulus, Shear modulus, Poisson ratio, and electrical resistivity. The measurement protocol consists of functional validation, calibration, and automated data acquisition.

This report presents information that is deemed important for individuals and communities to know and understand about the Earth's climate, impacts of climate change, and approaches to adaptation or mitigation.

From abstract: In 1995, 12 undersized, weaned female Hawaiian monk seal pups were captured at French Frigate Shoals in the Northwestern Hawaiian Islands... Eleven of the pups developed clinical signs of an eye disease between 12 and 46 days after capture... The cause of the eye disease and the site where it originated remain unknown.

This Closure Report (CR) presents information supporting the closure of Corrective Action Unit (CAU) 130: Storage Tanks, Nevada Test Site, Nevada. This CR complies with the requirements of the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management. The corrective action sites (CASs) within CAU 130 are located within Areas 1, 7, 10, 20, 22, and 23 of the Nevada Test Site. Corrective Action Unit 130 is comprised of the following CASs: • 01-02-01, Underground Storage Tank • 07-02-01, Underground Storage Tanks • 10-02-01, Underground Storage Tank • 20-02-03, Underground Storage Tank • 20-99-05, Tar Residue • 22-02-02, Buried UST Piping • 23-02-07, Underground Storage Tank This CR provides documentation supporting the completed corrective action investigations and provides data confirming that the closure objectives for CASs within CAU 130 were met. To achieve this, the following actions were performed: • Reviewed the current site conditions, including the concentration and extent of contamination. • Implemented any corrective actions necessary to protect human health and the environment. • Properly disposed of corrective action and investigation-derived wastes. From August 4 through September …

Dozens of groups have submitted energy, environmental, and economic recovery plans for consideration by the Obama administration and the 111th Congress. This report provides a comparative analysis of 12 national proposals, focusing especially on energy efficiency (EE) and renewable energy (RE) market and policy issues.

This is a progress report on polynomial system solving for statistical modeling. This is a progress report on polynomial system solving for statistical modeling. This quarter we have developed our first model of shock response data and an algorithm for identifying the chamber cone containing a polynomial system in n variables with n+k terms within polynomial time - a significant improvement over previous algorithms, all having exponential worst-case complexity. We have implemented and verified the chamber cone algorithm for n+3 and are working to extend the implementation to handle arbitrary k. Later sections of this report explain chamber cones in more detail; the next section provides an overview of the project and how the current progress fits into it.

Graphs of composite data products produced by DOE's Controlled Hydrogen Fleet and Infrastructure Demonstration and Validation project through March 2009.

Global Solar's CIGS manufacturing cost has decreased by increased automation, higher materials utilization, and greater capacity with higher rates in all tools.

This report documents progress made during FY 2008 in studies of converting the High Flux Isotope Reactor (HFIR) from highly enriched uranium (HEU) fuel to low-enriched uranium (LEU) fuel. Conversion from HEU to LEU will require a change in fuel form from uranium oxide to a uranium-molybdenum alloy. With axial and radial grading of the fuel foil and an increase in reactor power to 100 MW, calculations indicate that the HFIR can be operated with LEU fuel with no degradation in reactor performance from the current level. Results of selected benchmark studies imply that calculations of LEU performance are accurate. Scoping experiments with various manufacturing methods for forming the LEU alloy profile are presented.

The project objective is to study structure-property relations in solid solutions of nitrides and oxides with surrogate elements to simulate the behavior of fuels of inert matrix fuels of interest to the Advanced Fuel Cycle Initiative (AFCI), with emphasis in zirconium-based materials. Work with actual fuels will be carried out in parallel in collaboration with Los Alamos National Laboratory (LANL). Three key aspects will be explored: microstructure characterization through measurement of global texture evolution and local crystallographic variations using Electron Backscattering Diffraction (EBSD); determination of mechanical properties, including fracture toughness, quasi-static compression strength, and hardness, as functions of load and temperature, and, finally, development of structure-property relations to describe mechanical behavior of the fuels based on experimental data. Materials tested will be characterized to identify the mechanisms of deformation and fracture and their relationship to microstructure and its evolution. New aspects of this research are the inclusion of crystallographic information into the evaluation of fuel performance and the incorporation of statistical variations of microstructural variables into simplified models of mechanical behavior of fuels that account explicitly for these variations. The work is expected to provide insight into processing conditions leading to better fuel performance and structural reliability during manufacturing and …

This project concerns the replacement of the catalytic bed in a microturbine with a thermal oxidizer. The advantage of a thermal oxidizer over a traditional combustion chamber is that the length and temperature of the device allows the volatile species to oxidize relatively slowly and without a flame front. With no flame, the temperature increase throughout the unit is spread over a much larger volume so there is no hot spot for thermal NO{sub x} formation, and the gas Btu level does not have to be above the ignition concentration. Project specific objectives included assessment of the materials and performance requirements of the thermal oxidizer, design the thermal oxidizer system, fabrication of the thermal oxidizer, testing of the oxidizer's performance in concert with the microturbine and comparison of the performance of the oxidizer with catalytic beds and traditional combustion chambers. The thermal oxidizer was designed and fabricated with the assistance of High Country Fabrication of Casper, Wyoming. The design consists of a long set of tubes surrounded by a packed bed of loose ceramic material. The outer vessel containing the tubes and packing is a 3-foot diameter steel shell with multiple layers of thermal insulation. After the metal components were …

The U.S. Department of Energy is developing next generation processing methods to recycle uranium and transuranic (TRU) isotopes from spent nuclear fuel. The objective of the 3-year project described in this report was to develop near-term options for storing TRU oxides isolated through the uranium extraction (UREX+) process. More specifically, a Zircaloy matrix cermet was developed as a storage form for transuranics with the understanding that the cermet also has the ability to serve as a inert matrix fuel form for TRU burning after intermediate storage. The goals of this research projects were: 1) to develop the processing steps required to transform the effluent TRU nitrate solutions and the spent Xircaloy cladding into a zireonium matrix cermet sotrage form; and 2) to evaluate the impact of phenomena that govern durability of the storage form, material processing, and TRU utiliztion in fast reactor fuel. This report represents a compilation of the results generated under this program. The information is presented as a brief technical narrative in the following sections with appended papers, presentations and academic theses to provide a detailed review of the project's accomplishments.