This document describes the proposed strategy for disposal of spent and failed melters from the tank waste treatment plant to be built by the Office of River Protection at the Hanford site in Washington. It describes program management activities, disposal and transportation systems, leachate management, permitting, and safety authorization basis approvals needed to execute the strategy.

The goal of this joint LLNL-CalEnergy project is to develop a method for precipitating marketable silica from spent Salton Sea Geothermal Field (SSGF) brines. Many markets for silica exist. We have initially targeted production of silica as a rubber additive. Silica reinforced rubber gives tires less rolling resistance, greater tear strength, and better adhesion to steel belts. Previous silica precipitates produced by CalEnergy from Salton Sea brines were not suitable as rubber additives. They did not to disperse well in the rubber precursors and produced inferior rubber. CalEnergy currently minimizes silica scaling in some of their production facilities by acidifying the brine pH. The rate of silica precipitation slows down as the pH is lowered, so that energy extraction and brine reinfection are possible without unacceptable amounts of scaling even with more than 700 ppm SiO{sub 2} in solution. We are adding a step in which a small amount of base is added to the acidified brine to precipitate silica before reinfection. By carefully controlling the type, rate, and amount of base addition, we can optimize the properties of the precipitate to approach those of an ideal rubber additive.

Milestone M-45-09E of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement or TPA) [TPA 1996] requires submittal of an annual progress report on the development of waste tank leak detection, monitoring, and mitigation (LDMM) activities associated with the retrieval of waste from single-shell tanks (SSTs). This report details progress for fiscal year 2000, building on the current LDMM strategy and including discussion of technologies, applications, cost, schedule, and technical data. The report also includes discussion of demonstrations conducted and recommendations for additional testing. Tri-Party Agreement Milestones M-45-08A and M-45-08B required design and demonstration of LDMM systems for initial retrieval of SST waste. These specific milestones have recently been deleted as part of the M-45-00A change package. Future LDMM development work has been incorporated into specific technology demonstration milestones and SST waste retrieval milestones in the M-45-03 and M-45-05 milestone series.

The purpose of the Authorization Agreement is to serve as a mechanism whereby the U.S. Department of Energy, Richland Operations Office (RL) and Fluor Hanford (FH) jointly clarify and agree to key conditions for conducting work safely and efficiently in the Fast Flux Test Facility (FFTF). Work must be accomplished in a manner that achieves high levels of quality while protecting the environment and the safety and health of workers and the public, and complying with applicable contractual and regulatory requirements. It is the intent of this Agreement to address those items of significant importance in establishing and supporting the FFTF Authorization Envelope, but this Agreement in no way alters the terms and conditions of the Project Hanford Management Contract (PHMC), Contract Number DE-AC06-96RL13200.

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ABSIM (an acronym for ABsorption SIMulation) is a user-oriented computer code designed for the simulation of absorption systems at steady state, in both flexible and modular form. ABSIM makes it possible to investigate various cycle configurations with different working fluids, to calculate their operating parameters, to predict their performance and to compare them with each other on a uniform basis. A graphical user interface enables the user to draw the cycle diagram on the computer screen, enter data interactively, run the program and view the results either in the form of a table or superimposed on the cycle diagram. Special utilities enable the user to plot the results and produce a pressure-temperature-concentration (P-T-X) diagram of the cycle. Most absorption systems consist of a number of standard components or units (e.g., absorber, condenser) that may be combined in different forms to produce various cycles. Recognizing this, ABSIM has been structured around unit subroutines, each of which contains the governing equations for the particular unit. These subroutines are activated by a main program that interprets the input for the cycle, calls the units, and links them to each other in an order corresponding to the user's specification to form the complete system. …

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The purpose of the Double Shell Tanks (DST) and Waste Feed Delivery (WFD) Management Assessment Plan is to define how management assessments within DST h WFD will be conducted. The plan as written currently includes only WFD Project assessment topics. Other DST and WFD group assessment topics will be added in future revisions.

The objective of this task was to provide processing information data summaries on powder metallurgy (PM) alloys that meet the partner requirements for the production of low mass, highly accurate, near-net-shape powertrain components. This required modification to existing ISO machinability test procedures and development of a new drilling test procedure. These summaries could then be presented in a web page format. When combined with information generated from the USCAR CRADA this would allow chemical, metallurgical, and machining data on PM alloys to be available to all engineering and manufacturing personnel that have access to in-house networks. The web page format also allows for the additions of other wrought materials, making this a valuable tool to the technical staffs.

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This document provides a description of design verification and validation activities implemented by the Spent Nuclear Fuel (SNF) Project. During the execution of early design verification, a management assessment (Bergman, 1999) and external assessments on configuration management (Augustenburg, 1999) and testing (Loscoe, 2000) were conducted and identified potential uncertainties in the verification process. This led the SNF Chief Engineer to implement corrective actions to improve process and design products. This included Design Verification Reports (DVRs) for each subproject, validation assessments for testing, and verification of the safety function of systems and components identified in the Safety Equipment List to ensure that the design outputs were compliant with the SNF Technical Requirements. Although some activities are still in progress, the results of the DVR and associated validation assessments indicate that Project requirements for design verification are being effectively implemented. These results have been documented in subproject-specific technical documents (Table 2). Identified punch-list items are being dispositioned by the Project. As these remaining items are closed, the technical reports (Table 2) will be revised and reissued to document the results of this work.

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Renewable energy is derived from resources that are generally not depleted by human use, such as the sun, wind, and water movement. This report discusses various aspects of policy regarding renewable energy including tax credits and budget legislation.

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This plan includes the sampling, analysis, and quality assurance requirements for the 100-BC-5 Operable Unit on the USDOE Hanford Site.

This plan includes the sampling, analysis, and quality assurance requirements for the 100-FR-3 Operable Unit on the USDOE Hanford Site.

Oxidation testing of K Basin-stored N Reactor fuel in dry air, moist air, and moist helium provided reaction rate data for the Spent Nuclear Fuel Project. The tests were performed on small samples from two spent nuclear fuel elements retrieved from the closed canisters of the K West Basin. The spent nuclear fuel samples were tested using a thermogravimetric analysis system modified for moist-gas operation to allow testing in moist environments. The tests were run at constant temperature and water vapor pressure. The moist helium tests used 6.5 H a water vapor, producing seventeen data between 75 C and 210 C. Eight of these data were excluded from primary consideration due to testing anomalies and balance drift issues. Regression analysis of the nine acceptable data provided good assurance that the moist-helium results are consistent with literature data within the temperature range of 25 C to 210 C. Concerns about possible oxygen poisoning from air in-leakage and mass transfer limitations on the test data were reviewed. If oxygen poisoning occurred it was not likely to have biased the data sufficiently to change the basic conclusions of comparability to the literature data. Mass transfer limitations did not appear to have had significant …