Interesting plasmas in the laboratory and space are magnetized. General gyrokinetic theory is about a symmetry, gyro-symmetry, in the Vlasov-Maxwell system for magnetized plasmas. The most general gyrokinetic theory can be geometrically formulated. First, the coordinate-free, geometric Vlasov-Maxwell equations are developed in the 7-D phase space, which is defined as a fiber bundle over the space-time. The Poincar{copyright}-Cartan-Einstein 1-form pullbacked onto the 7-D phase space determines particles' worldlines in the phase space, and realizes the momentum integrals in kinetic theory as fiber integrals. The infinite small generator of the gyro-symmetry is then asymptotically constructed as the base for the gyrophase coordinate of the gyrocenter coordinate system. This is accomplished by applying the Lie coordinate perturbation method to the Poincar{copyright}-Cartan-Einstein 1-form, which also generates the most relaxed condition under which the gyro-symmetry still exists. General gyrokinetic Vlasov-Maxwell equations are then developed as the Vlasov-Maxwell equations in the gyrocenter coordinate system, rather than a set of new equations. Since the general gyrokinetic system-developed is geometrically the same as the Vlasov-Maxwell equations, all the coordinate independent properties of the Vlasov-Maxwell equations, such as energy conservation, momentum conservation, and Liouville volume conservation, are automatically carried over to the general gyrokinetic system. The pullback transformation …

In the currently envisioned configurations for heavy ion fusion, it is necessary to longitudinally compress the beam bunches by a large factor after the acceleration phase. Because the space-charge force increases as the beam is compressed, the beam size in the transverse direction will increase in a periodic quadrupole lattice. If an active control of the beam size is desired, a larger focusing force is needed to confine the beam in the transverse direction, and a non-periodic quadrupole lattice along the beam path is necessary. In this paper, we describe the design of such a focusing lattice using the transverse envelope equations. A drift compression and final focus lattice should focus the entire beam pulse onto the same focal spot on the target. This is difficult with a fixed lattice, because different slices of the beam may have different perveance and emittance. Four time-dependent magnets are introduced in the upstream of drift compression to focus the entire pulse onto the sam e focal spot. Drift compression and final focusing schemes are developed for a typical heavy ion fusion driver and for the Integrated Beam Experiment (IBX) being designed by the Heavy Ion Fusion Virtual National Laboratory.

During the 2001-2003 grant period, Institute for Fusion Studies (IFS) scientist made notable progress in a number of research areas. This report summarizes the work that has been accomplished in the following areas: (1) Magnetohydrodynamics; (2) Burning plasma and energetic particle physics; (3) Turbulent transport; (4) Computational physics; (5) Fundamental Theory; (6) Innovative confinement concepts; and (7) Plasma applications.

The compilation of Metal Waste Form (MWF) immersion test data in this document is part of the effort initiated to qualify the stainless steel-15% zirconium (SS-15Zr) alloy for repository disposal. The SS-15Zr alloy was developed as part of the waste stream from the Argonne National Laboratory (ANL) electrometallurgical process for spent nuclear fuel. There were four areas of significant relevance concerning MWF performance in a long-term repository setting addressed in the test model. The areas encompassed the study of the effects of (1) the solution aggressiveness [simulated by concentrated J13 solution (CJ13)], (2) high-chloride content of the solution [simulated by 10,000 ppm chloride solution (10KCl)], (3) solution pH [simulated by acidified J13 solution (AJ13)], and (4) the state of the metal surface--polished vs. oxidized on the releases. The simulated J-13 solution was intended to replicate the groundwater in the J-13 well at the Yucca Mountain geologic repository. A fifth area of interest was to determine if the releases were limited by iron saturation of the solution. The data obtained from the entire study will be compared with the data from the High Level Waste Glass (HLWG) form previously qualified for repository disposal. Even though the MWF samples used in these …

The possibility of an asymmetric ponderomotive barrier in a nonuniform dc magnetic field by high-frequency radiation near the cyclotron resonance for selected plasma species was contemplated in Physics of Plasmas 11 (November 2004) 5046-5064. Here we show that a similar one-way barrier, which reflects particles incident from one side while transmitting those incident from the opposite side, can be produced also in a uniform magnetic field, entirely due to inhomogeneity of high-frequency drive.

This report provides results from the second year of this three-year project to develop dilution measurement technology for characterizing PM2.5 (particles with aerodynamic diameter smaller than 2.5 micrometers) and precursor emissions from stationary combustion sources used in oil, gas and power generation operation. Detailed emission rate and chemical speciation tests results for a gas turbine, a process heater, and a commercial oil/gas fired boiler are presented. Tests were performed using a research dilution sampling apparatus and traditional EPA methods. A series of pilot tests were conducted to identify the constraints to reduce the size of current research dilution sampler for future stack emission tests. Based on the test results, a bench prototype compact dilution sampler developed and characterized in GE EER in August 2002.

The shallow water equations in a spherical geometry are solved using a 3-dimensional Cartesian method. Spatial discretization of the 2-dimensional, horizontal differential operators is based on the Cartesian form of the spherical harmonics and an icosahedral (spherical) grid. Computational velocities are expressed in Cartesian coordinates so that a problem with a singularity at the pole is avoided. Solution of auxiliary elliptic equations is also not necessary. A comparison is made between the standard form of the Cartesian equations and a rotational form using a standard set of test problems. Error measures and conservation properties of the method are reported for the test problems.

One type of attack on computer systems is know as a Denial of Service (DoS) attack. A DoS attack is designed to prevent legitimate users from using a system. Traditional Denial of Service attacks are done by exploiting a buffer overflow, exhausting system resources, or exploiting a system bug that results in a system that is no longer functional. In the summer of 1999, a new breed of attack has been developed called Distributed Denial of Service (DDoS) attack. Several educational and high capacity commercial sites have been affected by these DDoS attacks. A DDoS attack uses multiple machines operating in concert to attack a network or site. There is very little that can be done if you are the target of a DDoS. The nature of these attacks cause so much extra network traffic that it is difficult for legitimate traffic to reach your site while blocking the forged attacking packets. The intent of this paper is to help sites not be involved in a DDoS attack. The first tools developed to perpetrate the DDoS attack were Trin00 and Tribe Flood Network (TFN). They spawned the next generation of tools called Tribe Flood Network 2000 (TFN2K) and Stacheldraht (German …

To comply with the applicable requirements of the U.S. Department of Energy (USDOE) Order 435.1 and its associated Manual and Implementation Guide (USDOE 1999, USDOE 1999a, USDOE 1999b), this closure plan has been developed for the E-Area Low-Level Waste Facility (LLWF). The plan is organized according to the specifications of the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans (USDOE 1999d). Section 2 provides a brief overview of the general facility description, closure approach, closure schedule, related activities, and key assumptions. Sections 3 and 4 provide specific details of facility characteristics and the technical approach to closure, respectively, as well as supporting information. Additional schedule details re provided in Section 5. Section 6 provides a list of recommended items for consideration in association with future revisions to the E-Area LLWF Closure Pan and Performance Assessment (PA).

This report summarizes research on circulation and particle dynamics over the Middle Atlantic Bight shelf and upper slope. It includes an overview of the field experiments conducted in the waters off North Carolina, and gives the principal results from these experiments.

This Special Analysis (SA) addresses disposal of high-concentration I-129 wastes in the Intermediate Level (IL) Vaults at the Savannah River Site E-Area Low-Level Waste Facility. This SA addresses both the existing activated carbon vessels already placed in the IL Vault and any type of future waste that contains a high concentration of I-129. An equation is developed that relates a wasteform's vault inventory limit of I-129 to the wasteform's measured Kd. This SA was prepared to meet the requirements of the U.S. Department of Energy Order 435.1 (DOE 1999a). The order specifies that a performance assessment or SA should provide reasonable assurance that a low-level waste disposal facility will comply with the performance objectives of the Order. In addition to the performance objectives, the Order requires, for purposes of establishing limits on the concentration of radionuclides that may be disposed of near-surface, an assessment of impacts on water resources and on hypothetical persons assumed to inadvertently intrude for a temporary period into the low-level waste disposal facility.

This report summarizes the results of a feasibility study that evaluated solidification as an alternative treatment for organic waste.

The effect of disposing of low-level waste consisting of vitrified sludge from M-Area in slit trenches is evaluated.

The 500-700 m thick Yucca Mountain unsaturated zone (UZ) is under extensive investigation as a subsurface repository for the permanent disposal of high-level nuclear wastes. The site characterization has been mostly carried out for analyzing unsaturated flow and radionuclide transport under ambient, isothermal conditions. However, significant research effort has also been devoted to understand the nature of flow and transport processes under non-isothermal conditions. In particular, substantial repository heating from radioactive waste decay has motivated investigations of the coupled thermo-hydrologic (TH) behavior of the UZ under repository heating and its potential impact on repository performance. Significant progress has been made in quantitative coupled TH studies in the last decade. Despite the significant advances made so far in modeling and understanding TH processes, the previous studies have been in general limited to modeling in 1-D and 2-D (instead of the full 3-D representation), and/or small spatial and temporal scale analysis. In addition to these limited modeling exercises, multidimensional modeling has been carried out for large-scale (at the scale of the entire mountain) TH analyses. However, these previous large, mountain-scale TH models utilized the effective continuum model (ECM), rather than the more rigorous dual-continuum model (DKM). This is primarily due to numerical …

Assessments of radiological dose from usage of groundwater potentially contaminated by the Saltstone Disposal Facility (Z-Area) were made for a hypothetical future resident farmer. These assessments were made using the routine aqueous release model LADTAP XL (C), which is the model used for demonstrating liquid pathway dose compliance at SRS. The dose factors used in LADTAP XL (C) are those specified by the Department of Energy.

The Fuel Retrieval System (FRS) Process Validation Procedure (Shen 1999) requires that a specified quantity of fuel processed through the Primary Cleaning Machine (PCM) be inspected for cleanliness during initial operational and process validation testing. Specifically, these inspections are performed to confirm that the PCM adequately cleans the fuel elements of canister sludge. The results of these inspections will be used to demonstrate that residual quantities of canister particulate on fuel elements loaded into Multi-Canister Overpacks (MCOs) are within projected levels used to establish safety basis limits (Sloughter 1998). The fuel inspections performed as part of the validation process will be conducted during the Hot Operations portion of the Phased Startup Initiative (PSI) of the Fuel Retrieval and Integrated Water Treatment Systems (Pajunen 1999). Hot Operations testing constitutes Phases 3 and 4 of the PSI. The fuel assemblies in all candidate canisters will be thoroughly inspected during these test phases (highly degraded fuel assemblies are exempt from inspection). During subsequent production operation of the FRS, only periodic (every tenth canister) inspections for cleanliness will be performed and documented. This document describes the specific processes and techniques that will be applied in performing the cleanliness inspections, and the methodology used to …

Achieving agreement between measured and calculated neutron activation data resulting from Hiroshima and Nagasaki A-bomb detonations has been a major problem since the early 1980's. This has been particularly true for the materials that are activated by thermal and epithermal neutrons. Since thermal and epithermal neutrons are not transported very far from the weapon, the local shielding environment around the measurement location can be very important. A set of calculations incorporating an average density local-environment material (mush) has been made to demonstrate that the local environment plays an important role in the calculation-measurement agreement process. The optimum solution would be to include the local environment in all thermal neutron response calculations.

This report summarizes the early results of the post irradiation examination of the 30 GWd/MT MOX Average Power Test Capsules (numbers 3 and 10). The purpose of this preliminary examination is to document and monitor the progress of the MOX Average Power Test Irradiation. The capsules and their fuel pins were found to be in excellent condition. Measurement of the fission gas release fraction (about 1.50 to 2.26%), preliminary fuel stack gamma scan measurements, and preliminary fuel pin diameter measurements indicate that the fuel is behaving as expected.

The objective of this project was to gain an insight into the modeling support needed for the understanding, design, and operation of trace metal/radionuclide bioremediation. To achieve this objective, a workshop was convened to discuss the elements such a model should contain. A ''protomodel'' was developed, based on the recommendations of the workshop, and was used to perform sensitivity analysis as well as some preliminary simulations in support for bioremediation test experiments at UMTRA sites. To simulate the numerous biogeochemical processes that will occur during the bioremediation of uranium contaminated aquifers, a time-dependent one-dimensional reactive transport model has been developed. The model consists of a set of coupled, steady state mass balance equations, accounting for advection, diffusion, dispersion, and a kinetic formulation of the transformations affecting an organic substrate, electron acceptors, corresponding reduced species, and uranium. This set of equations is solved numerically, using a finite element scheme. The redox conditions of the domain are characterized by estimating the pE, based on the concentrations of the dominant terminal electron acceptor and its corresponding reduced specie. This pE and the concentrations of relevant species are passed to a modified version of MINTEQA2, which calculates the speciation and solubilities of the species …

The Savannah River Technology Center (SRTC) was requested to investigate the effects of the addition of Pu and Gd from H-Canyon to Sludge Batch 3 (SB3). The effects on Sludge Receipt and Adjustment Tank (SRAT) processing were discussed in WSRC-TR-2002-00322, which also addressed iron and gadolinium solubility criticality concerns in the presence of sodium oxalate. Since this work was completed, SRTC was requested to provide additional data for solubility testing at higher levels of sodium oxalate. This report supplements WSRC-TR-2002-00322 and addresses testing at higher level that are considered bounding for DWPF SB3 ''sludge-only'' processing, as well as ''SB3'' with Actinide Removal Product'' processing.

The proposed activity provides the description of the Data Acquisition System for Tank 241-AZ-101. This description is documented in HNF-5572, Tank 241-AZ-101 Waste Retrieval Data Acquisition System (DAS). This activity supports the planned mixer pump tests for Tank 241-AZ-101. Tank 241-AZ-101 has been selected for the first full-scale demonstration of a mixer pump system. The tank currently holds over 960,000 gallons of neutralized current acid waste, including approximately 12.7 inches of settling solids (sludge) at the bottom of the tank. As described in Addendum 4 of the FSAR (LMHC 2000a), two 300 HP mixer pumps with associated measurement and monitoring equipment have been installed in Tank 241-AZ-101. The purpose of the Tank 241-AZ-101 retrieval system Data Acquisition System (DAS) is to provide monitoring and data acquisition of key parameters in order to confirm the effectiveness of the mixer pumps utilized for suspending solids in the tank. The suspension of solids in Tank 241-AZ-101 is necessary for pretreatment of the neutralized current acid waste and eventual disposal as glass via the Hanford Waste Vitrification Plant. HNF-5572 provides a basic description of the Tank 241-AZ-101 retrieval system DAS, including the field instrumentation and application software. The DAS is provided to fulfill requirements …

Approximately 40 mixed oxide materials were prepared and characterized primarily as to their thermal expansion and meltingpoint behavior. Of particular interest were those materials which were stable, had melting points in excess of 1,400 deg C, and had low thermal expansions. (auth)

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