In situ vitrification (ISV), developed by Pacific Northwest Laboratory and patented for the US Department of Energy, is one method used to stabilize contaminated soils in place. ISV involves inserting four electrodes in a square array into contaminated soil and applying an electrical potential to the electrodes. The soil is heated to above its melting point, and the molten zone expands with time to encompass the contaminated zone. After cooling, the resulting solid material is usually a mixture of glass and crystalline material that has a significantly higher resistance to leaching than did the original soils. Nonvolatile elements (most radionuclides and metals) are dissolved into the melt or encapsulated in glass if their solubility in the melt is low. Organic compounds tends to be pyrolyzed, with the decomposition products diffusing to the surface and combusting on exiting the molten zone. A hood is placed over the vitrification zone to collect off-gas particulates and volatiles into a processing trailer that scrubs contaminants from the off-gas. The current study identified key parameters and processes in the ISV melt cycle and developed an improved understanding of ISV. Analytical approximations for several properties of molten soil were determined from available data. Using a simplified …

Yields of H{sub 2}, N{sub 2}O, O{sub 2}, and N{sub 2}, in simulated waste solutions, containing high nitrate, nitrite, hydroxide and aluminate, were experimentally measured in the presence and absence of moderate concentrations of organic chelators and some of their degradation products. These yields were measured at 30 and 60{degrees}C. No effect of dose rate on yield of H{sub 2} was observed and the amount of H{sub 2} increases linearly with dose and with the concentration of the organic additive. The generation of N{sub 2}O was observed only when organic solutes were present and its yield was dose rate dependent. Rate constants for H atom abstraction from the organic component by free H atoms were determined and these were correlated with the efficiency of the organic solute and in the generation of H{sub 2}. The rate of thermal generation of H{sub 2} and N{sub 2}O was also measured and was found to substantially increase in solutions that were preirradiated, presumably due to the generation of radiolytic degradation products. Computer modeling of the radiolytic precesses show the yield of H{sub 2} is strongly dependent on the nitrite concentration; the yield decreases with increasing nitrite concentration. The yield will be only weakly …

Initial work on this project has shown that it is possible to convert ethane and propane in the presence of steam and oxygen over a catalyst comprising calcium-nickel-potassium oxide to both lower and higher hydrocarbons at temperatures in the range of 300--600{degree}C. Major amounts of CO{sub 2} are formed at the higher temperatures and conversions are relatively low at the lower temperatures. However, there are indications that the objective of preparing C{sub 6} to C{sub 12} olefins may be achieved by operating at intermediate temperatures and much higher space velocities than have thus far been used. It is proposed to do a systematic investigation making blank runs to distinguish between thermal and catalytic reactions and investigating modified catalysts such as calcium cobalt potassium oxide, calcium nickel sodium oxide, magnesium nickel potassium oxide, and others. A wide variety of operating conditions will be investigated. The catalytic reaction mechanism and the role of carbon on the catalyst will be investigated by experiments with carbon and oxygen isotopes.

Low energy collisions involving neutral excited states of hydrogen are being studied with vacuum ultraviolet spectroscopy. Atomic hydrogen is generated by focusing an energetic pulse of ArF, KrF, or YAG laser light into a cell of molecular hydrogen, where a plasma is created near the focal point. The H{sub 2} molecules in and near this region are dissociated, and the cooling atomic hydrogen gas is examined with laser and dispersive optical spectroscopy. In related experiments, we are also investigating neutral H + O and H + metal {minus} atom collisions in these laser-generated plasmas.

The safety and optimal performance of large, commercial, light-water reactors require the knowledge at all time of the neutron-flux distribution in the core. In principle, this information can be obtained by solving the time-dependent neutron diffusion equations. However, this approach is complicated and very expensive. Sufficiently accurate, real-time calculations (time scale of approximately one second) are not yet possible on desktop computers, even with fast-running, nodal kinetics codes. A semi-experimental, nodal synthesis method which avoids the solution of the time-dependent, neutron diffusion equations is described. The essential idea of this method is to approximate instantaneous nodal group-fluxes by a linear combination of K, precomputed, three-dimensional, static expansion-functions. The time-dependent coefficients of the combination are found from the requirement that the reconstructed flux-distribution agree in a least-squares sense with the readings of J ({ge}K) fixed, prompt-responding neutron-detectors. Possible numerical difficulties with the least-squares solution of the ill-conditioned, J-by-K system of equations are brought under complete control by the use of a singular-value-decomposition technique. This procedure amounts to the rearrangement of the original, linear combination of K expansion functions into an equivalent more convenient, linear combination of R ({le}K) orthogonalized modes'' of decreasing magnitude. Exceedingly small modes are zeroed to eliminate any …

As with many other linear algebra algorithms, devising a portable implementation of sparse Cholesky factorization that performs well on the broad range of computer architectures currently available is a formidable challenge. Even after limiting our attention to machines with only one processor, as we have done in this report, there are still several interesting issues to consider. For dense matrices, it is well known that block factorization algorithms are the best means of achieving this goal. We take this approach for sparse factorization as well. This paper has two primary goals. First, we examine two sparse Cholesky factorization algorithms, the multifrontal method and a blocked left-looking sparse Cholesky method, in a systematic and consistent fashion, both to illustrate the strengths of the blocking techniques in general and to obtain a fair evaluation of the two approaches. Second, we assess the impact of various implementation techniques on time and storage efficiency, paying particularly close attention to the work-storage requirement of the two methods and their variants.

We present the recent results obtained from a soft X-ray reflection imaging microscope in the Schwarzschild configuration. The microscope demonstrated a spatial resolution of 0.7 {mu}m with a magnification of 16 at 18.2 nm. The soft X-ray laser at 18.2 nm was used as an X-ray source. Mo/Si multilayers were coated on the Schwarzschild optics and the normal incidence reflectivity at 18.2 nm per surface was measured to be {approximately} 20 %. 18 refs., 6 figs.

This demonstration guidance manual has been prepared to assist Martin Marietta Energy Systems, Inc. (Energy Systems), staff in conducting demonstrations. It is prepared in checklist style to facilitate its use and assumes that Energy Systems personnel have project management responsibility. In addition to a detailed step-by-step listing of procedural considerations, a general checklist, logic flow diagram, and several examples of necessary plans are included to assist the user in developing an understanding of the many complex activities required to manage technology demonstrations. Demonstrations are pilot-scale applications of often innovative technologies to determine the commercial viability of the technologies to perform their designed function. Demonstrations are generally conducted on well-defined problems for which existing technologies or processes are less than satisfactory in terms of effectiveness, cost, and/or regulatory compliance. Critically important issues in demonstration management include, but are not limited to, such factors as communications with line and matrix management and with the US Department of Energy (DOE) and Energy Systems staff responsible for management oversight, budgetary and schedule requirements, regulatory compliance, and safety.

Pacific Northwest Laboratory (PNL) is conducting this study for Westinghouse Hanford Company (Westinghouse Hanford), a contractor for the US Department of Energy (DOE). The purpose of the work is to study possible mechanisms and fluid dynamics contributing to the periodic release of gases from the double-shell waste storage tanks at the Hanford Site in Richland, Washington. The waste inside the tank is generating and periodically releasing potentially flammable gases into the tank's vent system according to observations. Questions scientists are trying to answer are: (1) How are these gases generated (2) How did these gases become trapped (3) What causes the periodic gas releases (4) And, what is the mechanism of the gas releases To develop a safe mitigation strategy, possible physical mechanisms for the periodic release of flammable gases need to be understood. During initial work, PNL has obtained, correlated, analyzed, and compared data with expected physical properties, defined mechanisms; and prepared initial models of gas formation and retention. This is the second interim report summarizing the status of the work done to data.

Low-level liquid waste (LLLW) is currently contained in ten 50,000-gal storage and process tanks at Oak Ridge National Laboratory (ORNL) and as residual heels in an number of older tanks that are no longer in active use. Plans are being formulated to treat these wastes, along with similar LLLW that will be generated in the future, to yield decontaminated effluents that can be disposed of and stable solid waste forms that can be permanently stored. The primary purpose of this report is to summarize the performance of the most promising separations processes that are appropriate for treatment of the LLLW supernate solution to remove the two dominant radionuclides, {sup 137}Cs and {sup 90}Sr; to indicate how they can be integrated into an effective flowsheet; and to estimate the expected performance of such flowsheets in comparison to waste treatment requirements.

This report summarizes NIPER's research on four interrelated topics for Light Oil Steamflooding. Four interrelated topics are described: The methodology for measuring capillary pressure and wettability at elevated temperature, the use of silylating agents to convert water-wet Berea sandstones or unconsolidated quartz sands to oil-wetted surfaces, the evaluation of the thermal hydrolytic stability of these oil-wet surfaces for possible use in laboratory studies using steam and hot water to recover oil, and the effect of porous media of different wettabilities on oil recovery where the porous media is first waterflooded and then steamflooded.

In order to study the microscopic physics underlying observed L-mode current scaling, 1-1/2-d BALDUR has been used to simulate density and temperature profiles for high and low current, neutral beam heated discharges on TFTR with several semi-empirical, theoretically-based models previously compared for TFTR, including several versions of trapped electron drift wave driven transport. Experiments at TFTR, JET and D3-D show that I{sub p} scaling of {tau}{sub E} does not arise from edge modes as previously thought, and is most likely to arise from nonlocal processes or from the I{sub p}-dependence of local plasma core transport. Consistent with this, it is found that strong current scaling does not arise from any of several edge models of resistive ballooning. Simulations with the profile consistent drift wave model and with a new model for toroidal collisionless trapped electron mode core transport in a multimode formalism, lead to strong current scaling of {tau}{sup E} for the L-mode cases on TFTR. None of the theoretically-based models succeeded in simulating the measured temperature and density profiles for both high and low current experiments.

A transport code (TRANSP) is used to simulate future deuterium-tritium experiments (DT) in TFTR. The simulations are derived from 14 TFTR DD discharges, and the modeling of one supershot is discussed in detail to indicate the degree of accuracy of the TRANSP modeling. Fusion energy yields and {alpha}-particle parameters are calculated, including profiles of the {alpha} slowing down time, average energy, and of the Alfven speed and frequency. Two types of simulations are discussed. The main emphasis is on the DT equivalent, where an equal mix of D and T is substituted for the D in the initial target plasma, and for the D{sup O} in the neutral-beam injection, but the other measured beam and plasma parameters are unchanged. This simulation does not assume that {alpha} heating will enhance the plasma parameters, or that confinement will increase with T. The maximum relative fusion yield calculated for these simulations is Q{sub DT} {approx} 0.3, and the maximum {alpha} contribution to the central toroidal {beta} is {beta}{sub {alpha}}(0) {approx} 0.5%. The stability of toroidicity-induced Alfven eigenmodes (TAE) and kinetic ballooning modes (KBM) is discussed. The TAE mode is predicted to become unstable for some of the equivalent simulations, particularly after the termination …

Research conducted in this terminal year of support centered on three distinct areas: mAChR ligand localization in pancreas and the effect of Ca{sup +2} on localization, continuation of assessment of quaternized and neutral mAChR ligands for possible use as PET myocardial imaging agents, and initiation of a study to determine the relationship of the nAChR receptor to the cellular receptor for measles virus. Several tables and figures illustrating the results are included.

The main objectives of this project are: (1) To demonstrate the general applicability of Limestone Injection Multistage Burner (LIMB) technology by testing 3 coals and 4 sorbents (total of 12 coal/sorbent combinations) at the Ohio Edison Edgewater Plant. (2) To demonstrate that Coolside is a viable technology for improving precipitator performance and reducing sulfur dioxide emissions while acceptance operability is maintained. During the past quarter, activities for phase I, design and permitting, and phase II, construction, shakedown and start-up were completed for phase III, operation, data collection, reporting and disposition, activities continued with consol completing the revisions to the Coolside Topical report, the completion of LIMB Extension testing, and the start of demobilization and restoration.

This report summarizes the progress of the Basic Sciences Branch of the National Renewable Energy Laboratory (NREL) from October 1, 1989, through September 30, 1990. Six technical sections of the report cover these main areas of NREL's in-house research: Semiconductor Crystal Growth, Amorphous Silicon Research, Polycrystalline Thin Films, III-V High-Efficiency Photovoltaic Cells, Solid-State Theory, and Solid-State Spectroscopy. Each section of the report was written by the group leader principally in charge of the work. The task in each case was to explain the purpose and major accomplishments of the work in the context of the US Department of Energy's National Photovoltaic Research Program plans.

This report identifies steps leading to manufacturing large volumes of low-cost, large-area photovoltaic (PV) modules. Both crystalline silicon and amorphous silicon technologies were studied. Cost reductions for each step were estimated and compared to Solarex Corporation's manufacturing costs. A cost model, a simple version of the SAMICS methodology developed by the Jet Propulsion Laboratory (JPL), projected PV selling prices. Actual costs of materials, labor, product yield, etc., were used in the cost model. The JPL cost model compared potential ways of lowering costs. Solarex identified the most difficult technical challenges that, if overcome, would reduce costs. Preliminary research plans were developed to solve the technical problems. 13 refs.

This report provides information on the recent commercial progress of inventions supported by the US Department of Energy's Energy-Related Inventions Programs (ERIP). It describes the results of the latest in a series of ERIP evaluation projects that have been completed since 1980. It focuses on the economic impacts of the program, notably sales and employment benefits. The period of interest is 1980 through 1990. The evaluation is based on data collected through mail and telephone surveying of 143 participants in the Program. As of October 1989, a total of 486 inventions were recommended to DOE by the National Institute for Standards and Technology, which screens all submitted inventions in terms of technical merit, potential for commercial success, and potential energy impact. By the end of 1990, at least 109 of these inventions had entered the market, generating total cumulative sales of more than $500 million. With $25.7 million in grants awarded from 1975 through 1990, and $63.1 million in program appropriations over the same period, ERIP has generated a 20:1 return in terms of sales values to grants, and an 8:1 return in sales versus program appropriations. It is estimated that 25% of all ERIP inventions had achieved sales by …

Partitioning the actinides in light-water reactor spent fuel and transmuting them in actinide-burning liquid-metal reactors has been proposed as a potential method for reducing the public risks from geologic disposal of nuclear waste. As a first step towards quantifying the benefits for waste disposal of actinide burning, we have calculated the release rates of key radionuclides from waste packages resulting from actinide burning, and compare them with release rates from LWR spent fuel destined for disposal at the potential repository at Yucca Mountain. The wet-drip water-contact mode has been used. Analytic methods and parameter values are very similar to those used for assessing Yucca Mountain as a potential repository. Once released, the transport characteristics of radionuclides will be largely determined by site geology. For the most important nuclides such as I-129 and {Tc}-99, which are undiminished by actinide-burning reactors, it is not surprising that actinide burning offers little reduction in releases. For important actinides such as Np-237 and Pu isotopes, which are reduced in inventory, the releases are not reduced because the release rates are proportional to solubility, rather than inventory.

At this point in time the literature is full of excellent review articles which describe the operating principles of optical systems for utilizing the unique radiation provided by synchrotron storage rings. In general, the perspective provided by this body of work is that of the end user-experimenter cum optics designer. Nominal design specifications of the accelerator are usually assumed, and the impact of operation in a performance envelope which may represent either degraded or enhanced machine performance is seldom considered. In this article, we have attempted to remove ourselves from this (our own usual) perspective and look instead at the beamline as a transfer function to map from the machine to the users experiment. We open first with an introduction to the perspective of the experimentalist, and some general considerations for the interaction of beamline hardware with the machine. We then discuss phase space representations of some common components of beamlines, and then treat some important classes of crystal and geometric optics in monochromators. We then close with a discussion of some of the common features of these optical systems, and the impact of the machine on user experiments.

This fourth revision of the Hanford Site National Environmental Policy (NEPA) Characterization presents current environmental data regarding the Hanford Site and its immediate environs. This information is intended for use in preparing Site-related NEPA documentation. In Chapter 4.0 are presented summations of up-to-date information about climate and meteorology, geology and hydrology, ecology, history and archaeology, socioeconomics, land use, and noise levels. Chapter 5.0 describes models, including their principal assumptions, that are to be used in simulating realized or potential impacts from nuclear materials at the Hanford Site. Included are models of radionuclides transport in groundwater and atmospheric pathways, and of radiation dose to populations via all known pathways from known initial conditions. Chapter 6.0 provides the preparer with the federal and state regulations, DOE orders and permits, and environmental standards directly applicable for environmental impact statements for the Hanford Site, following the structure Chapter 4.0. NO conclusions or recommendations are given in this report.

An analytical method which distinguishes between primary, secondary and tertiary amines has been developed. Trifluoroacetic anhydride, with 4-pyrrolidinopyridine as a catalyst, is used to form di- and mono-trifluoroacylated derivatives of primary and secondary aromatic amines, respectively. Tertiary aromatic amines such as quinoline do not react. GC/MS is then used to analyze the derivatized samples. Retention indices and response factors (relative to 4-fluoroaniline) are reported for >50 pure compounds known or expected to be present in fossil fuel base fractions. Also, results from the analysis of base fractions from mildly hydrotreated SRC II coal liquids and petroleum-derived light cycle oils will be reported.

A survey of wetlands on the Oak Ridge Reservation (ORR) was conducted in 1990. Wetlands occurring on ORR were identified using National Wetlands Inventory (NWI) maps and field surveys. More than 120 sites were visited and 90 wetlands were identified. Wetland types on ORR included emergent communities in shallow embayments on reservoirs, emergent and aquatic communities in ponds, forested wetland on low ground along major creeks, and wet meadows and marshes associated with streams and seeps. Vascular plant species occurring on sites visited were inventoried, and 57 species were added to the checklist of vascular plants on ORR. Three species listed as rare in Tennessee were discovered on ORR during the wetlands survey. The survey provided an intensive ground truth of the wetlands identified by NWI and offered an indication of wetlands that the NWI remote sensing techniques did not detect.

PCN is a system for developing and executing parallel programs. It comprises a high-level programming language, tools for developing and debugging programs in this language, and interfaces to Fortran and C that allow the reuse of existing code in multilingual parallel programs. Programs developed using PCN are portable across many different workstations, networks, and parallel computers. This document provides all the information required to develop parallel programs with the PCN programming system. In includes both tutorial and reference material. It also presents the basic concepts that underly PCN, particularly where these are likely to be unfamiliar to the reader, and provides pointers to other documentation on the PCN language, programming techniques, and tools. PCN is in the public domain. The latest version of both the software and this manual can be obtained by anonymous FTP from Argonne National Laboratory in the directory pub/pcn at info.mcs.anl.gov (c.f. Appendix A).