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The six coal fired power plants located in the Colorado Plateau and southern Rocky Mountain region of the U.S. produce 100 million tons of CO{sub 2} per year. Thick sequences of colocated sedimentary rocks represent potential sites for sequestration of the CO{sub 2}. Field and laboratory investigations of naturally occurring CO{sub 2}-reservoirs are being conducted to determine the characteristics of potential seal and reservoir units and the extent of the interactions that occur between the host rocks and the CO{sub 2} charged fluids. The results are being incorporated into a series of two-dimensional numerical models that represent the major chemical and physical processes induced by injection. During reporting period covered here (July 1 to September 30, 2003), the main achievements were: Preparation for Project Review visit in Salt Lake City by new Project Manager; Submittal of two scientific papers to a special issue of ''Chemical Geology'' on CO{sub 2} sequestration; Set-up of website reporting results of this project; and Publication of summary article in Utah Geological Survey ''Survey Notes'' (circulation of 3000).

The purpose of this report is to document the abstraction model being used in total system performance assessment (TSPA) model calculations for radionuclide transport in the unsaturated zone (UZ). The UZ transport abstraction model uses the particle-tracking method that is incorporated into the finite element heat and mass model (FEHM) computer code (Zyvoloski et al. 1997 [DIRS 100615]) to simulate radionuclide transport in the UZ. This report outlines the assumptions, design, and testing of a model for calculating radionuclide transport in the UZ at Yucca Mountain. In addition, methods for determining and inputting transport parameters are outlined for use in the TSPA for license application (LA) analyses. Process-level transport model calculations are documented in another report for the UZ (BSC 2004 [DIRS 164500]). Three-dimensional, dual-permeability flow fields generated to characterize UZ flow (documented by BSC 2004 [DIRS 169861]; DTN: LB03023DSSCP9I.001 [DIRS 163044]) are converted to make them compatible with the FEHM code for use in this abstraction model. This report establishes the numerical method and demonstrates the use of the model that is intended to represent UZ transport in the TSPA-LA. Capability of the UZ barrier for retarding the transport is demonstrated in this report, and by the underlying process …

The purpose of this report is to evaluate and document the screening of the clad degradation features, events, and processes (FEPs) with respect to modeling used to support the Total System Performance Assessment-License Application (TSPA-LA). This report also addresses the effect of certain FEPs on both the cladding and the commercial spent nuclear fuel (CSNF), DOE-owned spent nuclear fuel (DSNF), and defense high-level waste (DHLW) waste forms, as appropriate to address the effects on multiple materials and both components (FEPs 2.1.09.09.0A, 2.1.09.11.0A, 2.1.11.05.0A, 2.1.12.02.0A, and 2.1.12.03.0A). These FEPs are expected to affect the repository performance during the postclosure regulatory period of 10,000 years after permanent closure. Table 1-1 provides the list of cladding FEPs, including their screening decisions (include or exclude). The primary purpose of this report is to identify and document the analysis, screening decision, and TSPA-LA disposition (for included FEPs) or screening argument (for excluded FEPs) for these FEPs related to clad degradation. In some cases, where a FEP covers multiple technical areas and is shared with other FEP reports, this report may provide only a partial technical basis for the screening of the FEP. The full technical basis for shared FEPs is addressed collectively by the sharing …

The transition to collisionless ion-temperature-gradient-driven plasma turbulence is considered by applying dynamical systems theory to a model with ten degrees of freedom. Study of a four-dimensional center manifold predicts a ''Dimits shift'' of the threshold for turbulence due to the excitation of zonal flows and establishes the exact value of that shift in terms of physical parameters. For insight into fundamental physical mechanisms, the method provides a viable alternative to large simulations.

Measurements of high-frequency oscillations in JET [Joint European Torus], JT-60U, Alcator C-Mod, DIII-D, and TFTR [Tokamak Fusion Test Reactor] plasmas are contributing to a new understanding of fast ion-driven instabilities relevant to Advanced Tokamak (AT) regimes. A model based on the transition from a cylindrical-like frequency-chirping mode to the Toroidal Alfven Eigenmode (TAE) has successfully encompassed many of the characteristics seen in experiments. In a surprising development, the use of internal density fluctuation diagnostics has revealed many more modes than has been detected on edge magnetic probes. A corollary discovery is the observation of modes excited by fast particles traveling well below the Alfven velocity. These observations open up new opportunities for investigating a ''sea of Alfven Eigenmodes'' in present-scale experiments, and highlight the need for core fluctuation and fast ion measurements in a future burning-plasma experiment.

The Engineering Development Laboratory recently performed pulse jet mixer development studies related to Hanford's Waste Treatment Plant (WTP) Concentrate Receipt Vessel. These were performed on a wide variety of pulse jet arrangements, pulse jet sizes, nozzle diameters, nozzle configurations, nozzle velocities, pulse jet firing orders, and waste simulant rheologies. This paper describes the EDL Pulse Jet Mixing Test Stand capabilities, experimental methods and data acquisition.

Field and laboratory investigations of naturally occurring CO{sub 2}-reservoirs are being conducted to determine the characteristics of potential seal and reservoir units and the extent of the interactions that occur between the host rocks and the CO{sub 2} charged fluids. Efforts have focused on the Farnham Dome field, located in central Utah, and the Springerville-St. Johns field in Arizona and New Mexico. The Springerville-St. Johns field is particularly significant because of the presence of extensive travertine deposits that document release of CO{sub 2} to the atmosphere. CO{sub 2} accumulations at both fields occur in sedimentary rocks typical of CO{sub 2} reservoirs occurring on the Colorado Plateau. The main achievements during this quarter were: (1) a soil gas flux survey at the Springerville-St Johns field, (2) collection of some soil gas for chemical and isotopic analysis from this field, and (3) collection of travertine samples from an elevation range of over 1000 feet (330 m) for dating the time span of carbonate-saturated spring outflow at this field. Analytical results and interpretations are still in progress. When available they will allow contrast with soil gas measurements from Farnham Dome natural CO{sub 2} field in central Utah, which were reported in the previous …

Field and laboratory investigations of naturally occurring CO{sub 2}-reservoirs are being conducted to determine the characteristics of potential seal and reservoir units and the extent of the interactions that occur between the host rocks and the CO{sub 2} charged fluids. Efforts have focused on the Farnham Dome, located in central Utah, and the Springer-St. Johns field in Arizona and New Mexico. The Springer-St. Johns field is particularly significant because of the presence of extensive travertine deposits that document release of CO{sub 2} to the atmosphere. CO{sub 2} accumulations at both fields occur in sedimentary rocks typical of CO{sub 2} reservoirs occurring on the Colorado Plateau. The main achievements were: (1) to assess the possibility of CO{sub 2} leakage from the Farnham Dome of central Utah; and (2) prepare a paper for presentation at the 3rd Annual Conference on Carbon Sequestration.

Fusion power systems, if developed and deployed, would have many attractive features including power production not dependant on weather or solar conditions, flexible siting, and minimal carbon dioxide production. In this paper, we quantify the benefit of these features. In addition, fusion deployment scenarios are developed for the last half of this century and these scenarios are analyzed for resource requirements and waste production.

A new spectroscopic diagnostic on the National Spherical Torus Experiment (NSTX) measures the velocity distribution of ions in the plasma edge with both poloidal and toroidal views. An anisotropic ion temperature is measured during the presence of high-power high-harmonic fast-wave (HHFW) radio-frequency (RF) heating in helium plasmas, with the poloidal ion temperature roughly twice the toroidal ion temperature. Moreover, the measured spectral distribution suggests that two populations are present and have temperatures of 500 eV and 50 eV with rotation velocities of -50 km/s and -10 km/s, respectively. This bi-modal distribution is observed in both the toroidal and poloidal views (in both He{sup +} and C{sup 2+} ions), and is well correlated with the period of RF power application to the plasma. The temperature of the hot edge ions is observed to increase with the applied RF power, which was scanned between 0 and 4.3 MW. The ion heating mechanism is likely to be ion-Bernstein waves (IBW) from nonlinear decay of the launched HHFW.

The overall vision for FIRE [Fusion Ignition Research Experiment] is to develop and test the fusion plasma physics and plasma technologies needed to realize capabilities of the ARIES-RS/AT power plant designs. The mission of FIRE is to attain, explore, understand and optimize a fusion dominated plasma which would be satisfied by producing D-T [deuterium-tritium] fusion plasmas with nominal fusion gains {approx}10, self-driven currents of {approx}80%, fusion power {approx}150-300 MW, and pulse lengths up to 40 s. Achieving these goals will require the deployment of several key fusion technologies under conditions approaching those of ARIES-RS/AT. The FIRE plasma configuration with strong plasma shaping, a double null pumped divertor and all metal plasma-facing components is a 40% scale model of the ARIES-RS/AT plasma configuration. ''Steady-state'' advanced tokamak modes in FIRE with high beta, high bootstrap fraction, and 100% noninductive current drive are suitable for testing the physics of the ARIES-RS/A T operating modes. The development of techniques to handle power plant relevant exhaust power while maintaining low tritium inventory is a major objective for a burning plasma experiment. The FIRE high-confinement modes and AT-modes result in fusion power densities from 3-10 MWm{sup -3} and neutron wall loading from 2-4 MWm{sup -2} which …

A superconducting cavity used in a microwave gun requires that the launcher and the pickup probes be on the same side of the cavity, which causes direct coupling between them, or crosstalk. At room temperature, the crosstalk causes serious distortion of the RF response. This note addresses the phenomenon, the simulation results and the analysis, so that one can extract the desired information from the confusing signal.

Increased levels of blast furnace coal injection are needed to further lower coke requirements and provide more flexibility in furnace productivity. The direct injection of high temperature oxygen with coal in the blast furnace blowpipe and tuyere offers better coal dispersion at high local oxygen concentrations, optimizing the use of oxygen in the blast furnace. Based on pilot scale tests, coal injection can be increased by 75 pounds per ton of hot metal (lb/thm), yielding net savings of $0.84/tm. Potential productivity increases of 15 percent would yield another $1.95/thm. In this project, commercial-scale hot oxygen injection from a ''thermal nozzle'' system, patented by Praxair, Inc., has been developed, integrated into, and demonstrated on two tuyeres of the U.S. Steel Gary Works no. 6 blast furnace. The goals were to evaluate heat load on furnace components from hot oxygen injection, demonstrate a safe and reliable lance and flow control design, and qualitatively observe hot oxygen-coal interaction. All three goals have been successfully met. Heat load on the blowpipe is essentially unchanged with hot oxygen. Total heat load on the tuyere increases about 10% and heat load on the tuyere tip increases about 50%. Bosh temperatures remained within the usual operating range. …

This Phase I project was designed to demonstrate feasibility of in situ waste destruction and vitrification technology as a means of remediating hard-to-treat buried radioactive and hazardous wastes and focused on proving viability of the concentric graphite arc melter technique as a robust, safe, and economic tool for use as the IWDV process heat source. Oak Ridge National Laboratory provided technical support to Montec Research including the volatile behavior of elements during silicate melting operations and temperature viscosity modeling of silicate melts. Further research will be needed to develop this technology into a competitive remediation technique.

An assessment was performed to show the impact on airborne release fraction, respirable fraction, dose conversion factor and dose consequences of postulated accidents at the Plutonium Finishing Plant involving uranium dioxide rather than plutonium dioxide.

This Phase II research project was focused on constructing and testing a facility for the measurement of the structure of hot solid and liquid materials under extreme conditions using neutron diffraction. The work resulted in measurements at temperatures of 3300 K, the highest ever performed in a neutron beam. Work was performed jointly by Containerless Research, Inc. and Argonne National Laboratory with significant interactions with engineers and scientists at the under construction-SNS facility in Oak Ridge, TN. The work comprised four main activities: Design and construct an advanced instrument for structural studies of liquids and hot solids using neutron scattering. Develop and test a software package for instrument control, data acquisition and analysis. Test and demonstrate the instrument in experiments at the GLAD beamline at IPNS. Evaluate requirements for performing experiments at the SNS. Develop interest from the potential user base and identify potential support for Phase III. The objectives of the research were met. A second-generation instrument was developed and constructed. The instrument design drew on the results of a formal design review which was held at Argonne National Laboratory during the Phase I research [1]. The review included discussion with potential instrument users, SNS scientists and engineers and …

During the six months of funding we have focused first on the completion of the research begun at the University of Washington in the previous funding cycle. Specifically, we developed a method to polymerize oriented networks of microtubules on lithographically patterned surfaces (M.S. thesis Robert Doot). The properties of active transport have been studied detail, yielding insights into the dispersion mechanisms (Nitta et al.). The assembly of multifunctional structures with a microtubule core has been investigated (Ramachandran et al.). Isaac Luria (B.S. in physics, U. of Florida 2005) worked on the directed assembly of nanoscale, non-equilibrium structures as a summer intern. He is now a graduate student in my group at the University of Florida. T. Nitta and H. Hess: “Dispersion in Active Transport by Kinesin-Powered Molecular Shuttles”, Nano Letters, 5, 1337-1342 (2005) S. Ramachandran, K.-H. Ernst, G. D. Bachand, V. Vogel, H. Hess*: “Selective Loading of Kinesin-Powered Molecular Shuttles with Protein Cargo and its Application to Biosensing”, submitted to Small (2005)

The Bonneville Power Administration (BPA) has decided to amend its July 25, 2003, Record of Decision (ROD) regarding the proposed Summit/Westward Project (Project) to offer contract terms for an optional interconnection of this Project into the Federal Columbia River Transmission System (FCRTS). Under this optional interconnection plan, BPA would integrate electric power from the Project into the FCRTS at a point adjacent to Clatskanie People's Utility District (CPUD) existing Wauna Substation. In order to deliver power to this location, CPUD would develop a new substation (Bradbury Substation) at a site near the Project and a new 230-kV transmission line from there to CPUD's Wauna Substation, which is already connected to the FCRTS. As part of this revised decision, BPA will facilitate CPUD development of the Bradbury-Wauna transmission line by allowing joint use of BPA right-of-way. This will involve reconstructing a section of BPA's 115-kV Allston-Astoria No. 1 transmission line from single-circuit H-frame wood-pole design to double-circuit single metal pole design. Terms of BPA participation in CPUD's development of the Bradbury-Wauna transmission line will be documented in a Construction Agreement. This optional interconnection plan is in addition to BPA's previous offer for interconnection of the Project at BPA's Allston Substation, as …

The Conference on Super Intense Laser Atom Physics (SILAP) was held in November 2003 in Dallas, Texas. The venue for the meeting was South Fork Ranch in the outskirts of Dallas. The topics of the meeting included high harmonic generation and attosecond pulse generation, strong field interactions with molecules and clusters, particle acceleration, and relativistic laser atom interactions.

The authors have performed a number of imbibition tests with the treated and untreated cores in nC{sub 10}, nC{sub 14}, and nC{sub 16} and a natural gas condensate liquid. Imbibition tests for nC{sub 14} and nC{sub 16} were also carried out at elevated temperatures of 100 C and 140 C. An experimental polymer synthesized for the purpose of this project was used in core treatment. Imbibition results are very promising and imply liquid condensate mobility enhancement in the treated core. They also performed flow tests to quantify the increase in well deliverability and to simulate flow under realistic field conditions. In the past we have performed extensive testing of wettability alteration in intermediate gas wetting for polymer FC759 at temperatures of 24 C and 90 C. The results were promising for the purpose of gas well deliverability improvement in gas condensate wells. We used FC759 to lower the surface energy of various rocks. The model fluids nC{sub 10}, and nC{sub 14} were used to represent condensate liquid, and air was used as the gas phase. A new (L-16349) polymer, which has been recently synthesized for the purpose of the project, was used in the work to be presented here. L-16349 …