In this paper, a linearized four wheel steering (4WS) system model is deduced and then modified into a form which is appropriate for applying Matlab {mu} Toolbox to design robust controller. Several important topics are discussed in detail, such as (1) how to make system set-up match Matlab {mu} Toolbox requirement, (2) how to select weights based on plant`s uncertainty, (3) how to solve controller discretization problem, and (4) how to adjust the system so that the conditions necessary for using a state-space formula to solve H{infinity} optimal (sub-optimal) problem and performing the Matlab {mu} Toolbox D--K iteration procedure are satisfied. Finally simulation results of robust controller and a PID controller are compared.

Analysis of crosswell and three-component seismic data integrated with well logs have produced information on the distribution of subsurface heterogeneities below the In-Tank Precipitation facility at the Savannah River Site (SRS). The travel time P-wave tomogram and reflection imaging delineate lateral and vertical structural details of the formations. In particular, the high-resolution P-wave tomogram captures a low-velocity zone within the carbonates. This zone is surrounded by reflection events between depths of 150 and 200 ft. in the reflection imaging. The reflections are caused by the acoustic impedance contrast between the low velocity zone of `soupy` sand mixtures of unconsolidated materials and the more rigid and dense competent surrounded medium. The time-frequency analysis of full waveforms particle velocity identifies guided waves in form of leaky and normal modes at the depths of about 138 to 150 ft. This resulting change in lithology associated with the presence of guided waves is consistent with a velocity low observed in the vertical velocity profile determined from the inversion of three-component seismic data. This low-velocity zone intercepted by the wells H-BOR-34 and H-BOR-50 correlates with the conductive Griffins Landing Member, which is located above the carbonates. The result of the experiments demonstrate that the present …

Optical parametric oscillators (OPOS) are useful devices to generate tunable radiation. The tuning characteristics of OPOs can lead to their utility in remote sensing applications. We have investigated injection-seeded OPOs to generate narrow-band Mid-JR radiation for this purpose. OPOs exhibit a resonance structure similar to that of a laser`s cavity limiting the frequency choices available. Also, the coupling of the electric fields of the three interacting waves can generate cavity resonances for OPOs which have no cold cavity resonances (i.e. non-resonant OPOS). The potential for generating multiple frequencies simultaneously from a single OPO is discussed. The generation of multiple output frequencies is accomplished by injecting either multiple signal or multiple pump frequencies to the OPO. A seeded SRO is found to be well-suited to generating spectrally pure and stable multi-line output when the input pump field is multiple frequency. The generation of sideband frequencies during multiple seeding is also observed experimentally and addressed theoretically. The spectral purity of the OPO output is related to the frequency separation of the multi-line input as compared to the OPO cavity resonance structure.

Pressures are mounting for a regime to verify the dismantlement of US and Russian warheads, as well as a system of international control over the weapons` fissile materials to assure irreversibility. There are at least four motivating factors for these measures: (1) as the United States and Russia lower their numbers of nuclear weapons, each side seeks assurance that the warheads are actually being dismantled; (2) by accounting for the fissile materials and placing them under effective controls, the potential for smuggling and theft is reduced; (3) a fissile materials cutoff is being discussed at the Conference on Disarmament in Geneva; verification of a US-Russian cutoff, as well as substantial reductions in fissile materials stockpiles, are seen as integral to the cutoff; (4) calls for total nuclear disarmament have greatly increased; dismantlement verification and international control of fissile materials are widely viewed as requisite steps toward this goal. There are many questions to be answered before the United States can agree to a warhead verification regime and international control over excess fissile materials, let alone total nuclear disarmament. Two of the most important are: What are the prospects for effective verification? and How much fissile material can be declared as …

This paper explores two issues on TOP performance over ATM networks: ABR parameter tuning and performance comparison of binary mode ABR with enhanced UBR services. Of the fifteen parameters defined for ABR, two parameters dominate binary mode ABR performance: Rate Increase Factor (RIF) and Rate Decrease Factor (RDF). Using simulations, we study the effects of these two parameters on TOP over ABR performance. We compare TOP performance with different ABR parameter settings in terms of through-puts and fairness. The effects of different buffer sizes and LAN/WAN distances are also examined. We then compare TOP performance with the best ABR parameter setting with corresponding UBR service enhanced with Early Packet Discard and also with a fair buffer allocation scheme. The results show that TOP performance over binary mode ABR is very sensitive to parameter value settings, and that a poor choice of parameters can result in ABR performance worse than that of the much less expensive UBR-EPD scheme.

Production scale separation of tritium from other hydrogen isotopes at the Savannah River Site (SRS) in Aiken, SC, has been accomplished by several methods. These methods include thermal diffusion (1957--1986), fractional absorption (1964--1968), and cryogenic distillation (1967-present). Most recently, the Thermal Cycling Absorption Process (TCAP), a metal hydride based hydrogen isotope separation system, began production in the Replacement Tritium Facility (RTF) on April 9, 1994. TCAP has been in development at the Savannah River Technology Center since 1980. The production startup of this semi-continuous gas chromatographic separation process is a significant accomplishment for the Savannah River Site and was achieved after years of design, development, and testing.

The Lawrence Livermore National Laboratory (LLNL) Plutonium Facility conducts numerous programmatic activities involving plutonium to include device fabrication, development of improved and/or unique fabrication techniques, metallurgy research, and laser isotope separation. A Safety Analysis Report (SAR) for the building 332 Plutonium Facility was completed in July 1994 to address operational safety and acceptable risk to employees, the public, government property, and the environmental. This paper outlines the PRA analysis of the Evaluation Basis Fire (EBF) operational accident. The EBF postulates the worst-case programmatic impact event for the Plutonium Facility.

The most serious challenges in the design of chambers for inertial fusion energy (IFE) are 1) protecting the first wall from fusion energy pulses on the order of several hundred megajoules released in the form of x rays, target debris, and high energy neutrons, and 2) operating the chamber at a pulse repetition rate of 5-10 Hz (i.e., re-establishing, the wall protection and chamber conditions needed for beam propagation to the target between pulses). In meeting these challenges, designers have capitalized on the ability to separate the fusion burn physics from the geometry and environment of the fusion chamber. Most recent conceptual designs use gases or flowing liquids inside the chamber. Thin liquid layers of molten salt or metal and low pressure, high-Z gases can protect the first wall from x rays and target debris, while thick liquid layers have the added benefit of protecting structures from fusion neutrons thereby significantly reducing the radiation damage and activation. The use of thick liquid walls is predicted to 1) reduce the cost of electricity by avoiding the cost and down time of changing damaged structures, and 2) reduce the cost of development by avoiding the cost of developing a new, low-activation material. …

The Idaho National Engineering and Environmental Laboratory (INEEL) is aggressively managing waste with no identified path to disposal (WNPD), which was previously termed special case waste (SCW). As a result of several years of this aggressive management, the INEEL has reduced its WNPD volume from approximately 38,000 m{sup 3} in 1993 to approximately 6.33 m{sup 3} in 1999. This paper discusses how the INEEL reduced its WNPD volume. It specifically discusses the beryllium reflector waste produced from the Advanced Test Reactor (ATR) as an example of the INEEL's success in managing its WNPD. The INEEL's success in reducing its WNPD volume is the result of establishing long-range strategic objectives and consistently allocating an annual budget to implement specific work tasks that are consistent with these objectives. In addition, specific short- and long-range work tasks were developed and documented in work control documents. The work tasks are evaluated annually for consistency with the strategic objectives. Since the INEEL has successfully reduced its WNPD volume, it is now focusing on disposing of the remaining volume and preventing future generation of WNPD. As a result of this focused effort, a life-cycle disposal plan was developed for the Advanced Test Reactor (ATR) beryllium waste. …

Small quantities of transuranic (TRU) waste represent a significant challenge to the waste disposition and facility closure plans of several sites in the Department of Energy (DOE) complex. This paper presents the results of a series of evaluations, using a systems engineering approach, to identify the preferred alternative for dispositioning TRU waste from small quantity sites (SQSs). The TRU waste disposition alternatives evaluation used semi-quantitative data provided by the SQSs, potential receiving sites, and the Waste Isolation Pilot Plant (WIPP) to select and recommend candidate sites for waste receipt, interim storage, processing, and preparation for final disposition of contact-handled (CH) and remote-handled (RH) TRU waste. The evaluations of only four of these SQSs resulted in potential savings to the taxpayer of $33 million to $81 million, depending on whether mobile systems could be used to characterize, package, and certify the waste or whether each site would be required to perform this work. Small quantity shipping sites included in the evaluation included the Battelle Columbus Laboratory (BCL), University of Missouri Research Reactor (MURR), Energy Technology Engineering Center (ETEC), and Mound Laboratory. Candidate receiving sites included the Idaho National Engineering and Environmental Laboratory (INEEL), the Savannah River Site (SRS), Los Alamos National …

Interference lithography is an emerging, technology that provides a means for achieving high resolution over large exposure areas (approximately 1 m{sup 2}) with virtually unlimited depth of field. One- and two-dimensional arrays of deep submicron structures can be created using near i-line wavelengths and standard resist processing. In this paper, we report on recent advances in the development of this technology, focusing, in particular, on how exposure latitude and resist profile scale with interference period We present structure width vs dose curves for periods ranging from 200 nm to 1 um, demonstrating that deep submicron structures can be generated with exposure latitudes exceeding 30%. Our experimental results are compared to simulations based on PROLITIV2.

Groundwater monitoring has detected tritium ({sup 3}H) and {sup 22}Na contamination down gradient from the Brookhaven LINAC Isotope Producer (BLIP), located at Brookhaven National Laboratory (BNL). Site characterization studies indicate that the BLIP is the source of contamination. The highest measured values for {sup 3}H were 52,400 pCi/L recorded less than 100 feet south (down gradient) of the BLIP facility. The BLIP produces radioisotopes that are crucial in nuclear medicine for both research and clinical use. The BLIP also supports research on diagnostic and therapeutic radiopharmaceuticals. During operation a proton beam impinges a target (typically salts encapsulated in stainless steel) to produce the required radioisotopes. The proton beam is completely absorbed prior to reaching the soils surrounding the target shaft. However, secondary neutrons are produced that reach the soil causing activation products to form. Among the longer-lived isotopes of concern are tritium and {sup 22}Na. Both of these isotopes have the potential to negatively impact the groundwater below the BLIP. Several corrective actions have been implemented at the BLIP facility in response to tritium detection in the groundwater. The first actions were to improve surface water management (e.g. storm water down spouts) and the installation of a gunite cap around …

Hydrous Pyrolysis / Oxidation (HPO) is an in situ thermal remediation technology that uses hot, oxygenated groundwater to completely mineralize a wide range of organic pollutants. A field demonstration of HPO was performed at a creosote contaminated site during the summer of 1997. The groundwater was heated by steam injections and oxygen was added by coinjection of compressed air. The remediation was monitored from multiple groundwater monitoring wells. Dissolved organic carbon levels increased in response to steam injections as a result of the enhanced dissolution and mobilization of the creosote into the heated groundwater. Elevated concentrations of partially oxidized organic compounds (i.e. phenols, benzoic acid, fluorenone, anthrone and 9,10- anthracenedione), decreased levels of dissolved oxygen and isotopic shifts in the dissolved inorganic pool were indicators of partial to complete oxidative destruction of the creosote in the heated aquifer as a result of the HPO process.

Engineers at the Idaho National Engineering and Environmental Laboratory (INEEL) are investigating the use of a proprietary silicon-polymer to encapsulate high-level calcine waste stored at the INEEL's Idaho Nuclear Technology and Engineering Center (INTEC). The silicon-polymer-encapsulated waste may be suitable for direct disposal at a radioactive waste disposal facility or for transport to an offsite melter for further processing. In connection with silicon-polymer encapsulation, the University of Akron, under special arrangement with Orbit Technologies, the originator of the Polymer Encapsulation Technology (PET), has studied a simulated waste material from INTEC called pilot-scale calcine that contains hazardous materials but no radioactive isotopes. In this study, Toxicity Characteristic Leaching Procedure (TCLP) and Materials Characterization Center Test 1P were performed to test the waste form for disposal. In addition, a maximum waste loading was established for transporting the calcine waste at INTEC to an offsite melter. For this maximum waste loading, compressive strength testing, 10-m drop testing, melt testing, and a Department of Transportation (DOT) oxidizer test were performed.

Technologies were investigated to determine viable processes for removing mercury from the calciner (NWCF) offgas system at the Idaho National Engineering and Environmental Laboratory. Technologies for gas phase and aqueous phase treatment were evaluated. The technologies determined are intended to meet EPA Maximum Achievable Control Technology (MACT) requirements under the Clean Air Act and Resource Conservation and Recovery Act (RCRA). Currently, mercury accumulation in the calciner off-gas scrubbing system is transferred to the tank farm. These transfers lead to accumulation in the liquid heels of the tanks. The principal objective for aqueous phase mercury removal is heel mercury reduction. The system presents a challenge to traditional methods because of the presence of nitrogen oxides in the gas phase and high nitric acid in the aqueous scrubbing solution. Many old and new technologies were evaluated including sorbents and absorption in the gas phase and ion exchange, membranes/sorption, galvanic methods, and UV reduction in the aqueous phase. Process modifications and feed pre-treatment were also evaluated. Various properties of mercury and its compounds were summarized and speciation was predicted based on thermodynamics. Three systems (process modification, NOxidizer combustor, and electrochemical aqueous phase treatment) and additional technology testing were recommended.

Researchers from Brookhaven National Laboratory (BNL) tested perfluorocarbon (PFT) gas tracers on a subsurface barrier with known flaws at the Waldo test facility [operated by Science and Engineering Associates, Inc (SEA)]. The tests involved the use of five unique PFT tracers with a different tracer injected along the interior of each wall of the barrier. A fifth tracer was injected exterior to the barrier to examine the validity of diffusion controlled transport of the PFTs. The PFTs were injected for three days at a nominal flow rate of 15 cm{sup 3}/min and a concentrations in the range of a few hundred ppm. Approximately 65 liters of air laced with tracer was injected for each tracer. The tracers were able to accurately detect the presence of the engineered flaws. Two flaws were detected on the north and east walls and lane flaw was detected on the south and west walls. In addition, one non-engineered flaw at the seam between the north and east walls was also detected. The use of multiple tracers provided independent confirmation of the flaws and permitted a distinction between tracers arriving at a monitoring port after being released from a nearby flaw and non-engineered flaws. The PFTs …

A newly available neutron dose equivalent remmeter with improved sensitivity and energy response has been put into service at Rocky Flats Environmental Technology Site (RFETS). This instrument is being used to expedite measurement of the Transport Index and as an ALARA tool to identify locations where slightly elevated neutron dose equivalent rates exist. The meter is capable of measuring dose rates as low as 0.2 {mu}Sv per hour (20 {mu}rem per hour). Tests of the angular response and energy response of the instrument are reported. Calculations of the theoretical instrument response made using MCNP{trademark} are reported for materials typical of those being shipped.

This is one of two companion papers that describe the ENERGY-10 PV design tool computer simulation program. The other paper is titled ''ENERGY-10 Photovoltaics: A New Capability.'' Whereas this paper focuses on the PV aspects of the program, the companion paper focuses on the implementation method. The case study in this paper is a commercial building application, whereas the case study in the companion paper is a residential application with an entirely different building load characteristic. Together they provide a balanced view.

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Among CDF physics opportunities, heavy flavour physics is one of the most prominent and promising for the Tevatron run2. Still in the run1 CDF demonstrated that high precision CP violation measurement in the beauty sector as well as B mixing are feasible at hadronic collider, we think here especially to the first measure of sin2{beta} with B{sup 0} {yields} J/PsiK{sub s}{sup 0} decays and that of {Delta}m{sub Bd}. Tevatron accelerator and CDF detector upgrades are extensively discussed in other papers to which we refer to. Here we just recall the new features relevant to heavy flavour physics: New muon detector coverage up to |{eta}| < 1.5 and lower p{sub T} threshold for single and dimuon triggers. New Time of Flight detector (TOF) placed at R = 1.4m, made of 216 scintillator bars. The TOF resolution is 100 ps allowing a K/{pi} separation at 2 {sigma} for p{sub T} (K) < 1.6GeV. With this upgrade the effective dilution {epsilon}D{sup 2} of flavour tagging algorithms will reach 11.3 % (5.7 % in run1). Completely new Silicon Vertex detector SVXII of 5 double layers, other 2 external silicon layer ISL and additional silicon layer L00 at 1.5 cm from the beam pipe; will …

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The long-term program aimed at selection of a site for a deep repository was initiated in Finland in 1983. This program has come to end in 2001 and a new phase aimed at implementation of the geological disposal of spent fuel has been started. In this new phase the first milestone is the application for a construction license for the disposal facility around 2010. To fulfill the needs for detailed design of the disposal system, an underground rock characterization facility (URCF) will be constructed at the representative depth at Olkiluoto. The excavation of this facility will start the work for underground characterization, testing and demonstration, which is planned to be a continuous activity throughout the whole life cycle of the deep repository. The overall objectives for the underground site characterization are (1) verification of the present conclusions on site suitability, (2) definition and identification of suitable rock volumes for repository space and (3) characterization of planned host rock for detailed design, safety assessment and construction planning. The objective for verification aims at assessing that the Olkiluoto site meets the basic criteria for long-term safety and as well the basic requirements for construction and thus justifies the site selection. The two …

This paper describes the approaches used in the clearing, cleaning, decontamination and decommissioning of a very large suite of seven concrete shielded caves and other facilities used by UKAEA at Winfrith Technology Centre, England over a period of about 30 years for the postirradiation examination (PIE) of a wide range of nuclear fuels and other very active components. The basic construction of the facilities will first be described, setting the scene for the major challenges that 1970s' thinking posed for decommissioning engineers. The tendency then to use large and heavy items of equipment supported upon massive steel bench structures produced a series of major problems that had to be overcome. The means of solving these problems by utilization of relatively simple and inexpensive equipment will be described. Later, a further set of challenges was experienced to decontaminate the interior surfaces to allow man entries to be undertaken at acceptable dose rates. The paper will describe the types of tooling used and the range of complementary techniques that were employed to steadily reduce the dose rates down to acceptable levels. Some explanations will also be given for the creation of realistic dose budgets and the methods of recording and continuously assessing …