The Pittsburgh Energy Technology Center of the US Department of Energy has contracted with Combustion Engineering, Inc. (CE) to perform a five-year project on ``Combustion Characterization of Beneficiated Coal-Based Fuels.`` The beneficiated coals are produced by other contractors under the DOE Coal Preparation Program. Several contractor-developed advanced coal cleaning processes are run at pilot-scale cleaning facilities to produce 20-ton batches of fuels for shipment to CE`s laboratory in Windsor, Connecticut. CE then processes the products into either a coal-water fuel (CWF) or a dry microfine pulverized coa1 (DMPC) form for combustion testing. The objectives of this project include: (1) the development of an engineering data base which will provide detailed information on the properties of BCFs influencing combustion, ash deposition, ash erosion, particulate collection, and emissions; and (2) the application of this technical data base to predict the performance and economic impacts of firing the BCFs in various commercial boiler designs. During the third quarter of 1991, the following technical progress was made: Calculated the kinetic characteristics of chars from the combustion of spherical oil agglomeration beneficiated products; continued drop tube devolatilization tests of the spherical oil agglomeration beneficiated products; continued analyses of the data and samples from the CE …

Newsletter of the Gulf Coast Waste Disposal Authority discussing news and updates related to the organization's meetings and activities, changes to regulations, and other relevant information.

The following messages were taken from Inter-office Electronic Mail and provide perspective on the DOE FAST site survey. The key issue is that WSRC analytical groups have been unable to state when processes will be operated and what the exact requirements will be for characterizing materials from those processes when they do start. What results is a uncertainty at the site in the actual analytical work load. Although Donnan refers to the original survey data, one update was submitted to the needs requirements in the fall of 90. However that update was not as complete as the one given below. I have identified some of the people using brackets.

The COMMIX-1AR/P computer code is designed for analyzing the steady-state and transient aspects of single-phase fluid flow and heat transfer in three spatial dimensions. This version is an extension of the modeling in COMMIX-1A to include multiple fluids in physically separate regions of the computational domain, modeling descriptions for pumps, radiation heat transfer between surfaces of the solids which are embedded in or surround the fluid, a k-{var epsilon} model for fluid turbulence, and improved numerical techniques. The porous-medium formulation in COMMIX allows the code to be applied to a wide range of problems involving both simple and complex geometrical arrangements. The basic equations, underlying assumptions, and solution techniques are presented for the entire computer code, covering both old and new features.

The events of FY 1990 indicate that another successful year in the evolution of the Community Radiation Monitoring Program is in the books. The agencies and organizations involved in the program have developed a sound and viable working relationship, and it appears that the major objectives, primarily dispelling some of the concerns over weapons testing and radiation on the part of the public, are being effectively addressed. The program is certainly a dynamic operation, growing and changing to meet perceived needs and goals as more experience is gained through our work. The change in focus on our public outreach efforts will lead us to contacts with more students and schools, service clubs and special interest groups in the future, and will refine, and hopefully improve, our communication with the public. If that can be accomplished, plus perhaps influencing a few more students to stay in school and even grow up to be scientists, engineers and better citizens, we will be closer to having achieved our goals. It is important to note that the success of the program has occurred only because the people involved, from the Department of Energy, the Environmental Protection Agency, the Desert Research Institute, the University of …

An analysis of metal-, oxide, and nitride-fueled advanced liquid metal reactor cores was performed to investigate the calculated differences in sodium void reactivity, and to determine the relationship between sodium void reactivity and burnup reactivity swing using the three fuel types. The results of this analysis indicate that nitride fuel has the least positive sodium void reactivity for any given burnup reactivity swing. Thus, it appears that a good design compromise between transient overpower and loss of flow response is obtained using nitride fuel. Additional studies were made to understand these and other nitride advantages. 8 refs., 5 figs., 3 tabs.

The primary objective of this project is the investigation of the effects of pore structure on the capacity of porous metal oxides for removal of gaseous pollutants from flue gases of power plants (SO{sub 2}) and hot coal gas (primarily H{sub 2}S). Specifically, we intend to appropriately exploit the differences of the sulfidation and sulfation reactions (for instance, different molar volumes of solid products) to elucidate the dependence of the sorptive capacity of a porous sorbent on its physical microstructure.

The primary objective of this project is the investigation of the effects of pore structure on the capacity of porous metal oxides for removal of gaseous pollutants from flue gases of power plants (SO{sub 2}) and hot coal gas (primarily H{sub 2}S). Specifically, we intend to appropriately exploit the differences of the sulfidation and sulfation reactions (for instance, different molar volumes of solid products) to elucidate the dependence of the sorptive capacity of a porous sorbent on its physical microstructure.

Three distinct types of high toroidal mode number instabilities are obtained from a comprehensive kinetic calculation, using as input transport code results from the analysis of a recent design for the Burning Plasma Experiment (BPX). These instabilities are: the collisionless trapped-electron ion-temperature-gradient mode, the magnetohydrodynamic ballooning mode, and a high toroidal mode number version of the toroidicity-induced Alfven eigenmode or gap'' mode. The dependence of the instability linear eigenfrequencies on minor radius, beta, and toroidal mode number are investigated, along with the effects of hot alpha particles. Relative quasilinear fluxes of particles and energy for each species are also obtained. In addition, the beta dependence of the magnetohydrodynamic ballooning mode is investigated for a case using as input the results of a transport code calculation for the Tokamak Fusion Test Reactor (TFTR) in an extrapolation to a deuterium-tritium mixture. The effects of alpha particles and the relative quasilinear fluxes are also investigated for this case. 13 refs., 13 figs., 4 tabs.

The Congress of the United States requested that the Secretary of Energy: Prepare a report for the Congress that comprehensively inventories the sources of carbon dioxide (CO{sub 2}) and arranges the policy options to be formulated in cooperation with the Environmental Protection Agency (including, but not limited to, energy pricing, energy efficiency requirements, alternative fuels, alternative end use, and supply technology) which would lead to a substantial reduction in CO{sub 2} emissions. This paper summarizes work in progress to respond to the Congressional request. Further, it builds on the DOE's first National Energy Strategy (NES) (DOE 191). As a result of the substantial research effort in support of this report, five major conclusions are drawn and discussed.

The Congress of the United States requested that the Secretary of Energy: Prepare a report for the Congress that comprehensively inventories the sources of carbon dioxide (CO{sub 2}) and arranges the policy options to be formulated in cooperation with the Environmental Protection Agency (including, but not limited to, energy pricing, energy efficiency requirements, alternative fuels, alternative end use, and supply technology) which would lead to a substantial reduction in CO{sub 2} emissions. This paper summarizes work in progress to respond to the Congressional request. Further, it builds on the DOE`s first National Energy Strategy (NES) (DOE 191). As a result of the substantial research effort in support of this report, five major conclusions are drawn and discussed.

The rapid growth in the power of large-scale computers has had a revolutionary effect on the study of charged-particle accelerators that is similar to the impact of smaller computers on everyday life. Before an accelerator is built, it is now the absolute rule to simulate every component and subsystem by computer to establish modes of operation and tolerances. We will bypass the important and fruitful areas of control and operation and consider only application to design and diagnostic interpretation. Applications of computers can be divided into separate categories including: component design, system design, stability studies, cost optimization, and operating condition simulation. For the purposes of this report, we will choose a few examples taken from the above categories to illustrate the methods and we will discuss the significance of the work to the project, and also briefly discuss the accelerator project itself. The examples that will be discussed are: (1) the tracking analysis done for the main ring of the Superconducting Supercollider, which contributed to the analysis which ultimately resulted in changing the dipole coil diameter to 5 cm from the earlier design for a 4-cm coil-diameter dipole magnet; (2) the design of accelerator structures for electron-positron linear colliders and …

The objective of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation dose that individuals could have received as a result of emission from nuclear operations at Hanford since their inception in 1944. The purpose of this report is to outline the basic algorithm and necessary computer calculations to be used to calculate radiation doses specific and hypothetical individuals in the vicinity of Hanford. The system design requirements, those things that must be accomplished, are defined. The system design specifications, the techniques by which those requirements are met, are outlined. Included are the basic equations, logic diagrams, and preliminary definition of the nature of each input distribution. 4 refs., 10 figs., 9 tabs.

The deposition and growth of epitaxial thin films of YBa{sub 2}Cu{sub 3}O{sub 7} are modeled by means of Monte Carlo simulations of the deposition and diffusion of Y, Ba, and Cu oxide particles. This complements existing experimental characterization techniques to allow the study of kinetic phenomena expected to play a dominant role in the inherently non-equilibrium thin film deposition process. Surface morphologies and defect structures obtained in the simulated films are found to closely resemble those observed experimentally. A systematic study of the effects of deposition rate and substrate temperature during in-situ film fabrication reveals that the kinetics of film growth can readily dominate the structural formation of the thin film. 16 refs., 4 figs.

A modified binary collision approximation allowing the proper order of the collisions in time was used to study cascades in Cu and Au at primary kinetic energies up to 100 keV. Nonlinearities were approximated by letting already-stopped cascade atoms become targets in later collisions, using an improved method of locating potential targets to extend the calculations to energies much higher than heretofore. Beside the effect of the approximate nonlinearity, the effect of thermal disorder in the targets was examined. Target redisplacements reduce the damage in Cu by 3% at most, but in Au they reduce it by amounts up to 20% at 100 keV. Thermal disorder is also important: by disrupting crystal effects, the damage is reduced significantly. 11 refs., 4 figs.

This memorandum discusses five key issues that initial interviews have brought into focus: The preoccupation of the public with nuclear waste disposal, the credibility of public opinion polls addressing nuclear power, the unlikelihood of dramatic change in opinion by nuclear critics, difficulties in communicating technical concepts, and the problem of focussing narrowly or broadly on policy issues.

This memorandum discusses five key issues that initial interviews have brought into focus: The preoccupation of the public with nuclear waste disposal, the credibility of public opinion polls addressing nuclear power, the unlikelihood of dramatic change in opinion by nuclear critics, difficulties in communicating technical concepts, and the problem of focussing narrowly or broadly on policy issues.

Many robot control algorithms for high performance in-contact operations including hybrid force/position, stiffness control and impedance control approaches require the command the joint torques. However, most commercially available robots do not provide joint torque command capabilities. The joint command at the user level is typically position or velocity and at the control developer level is voltage, current, or pulse-width, and the torque generated is a nonlinear function of the command and joint position. To enable the application of high performance in-contact control algorithms to commercially available robots, and thereby facilitate technology transfer from the robot control research community to commercial applications, an methodology has been developed to linearize the torque characteristics of electric motor-amplifier combinations. A four degree of freedom Adept 2 robot, having pulse-width modulation amplifiers and both variable reluctance and brushless DC motors, is converted to operate from joint torque commands to demonstrate the methodology. The commercial robot controller is replaced by a VME-based system incorporating special purpose hardware and firmware programmed from experimental data. The performance improvement is experimentally measured and graphically displayed using three-dimensional plots of torque vs command vs position. The average percentage torque deviation over the command and position ranges is reduced from as …

Corrosion resistant materials are being considered for the metallic barrier of the Yucca Mountain Project`s high-level radioactive waste disposal containers. High nickel alloys and titanium alloys have good corrosion resistance properties and are considered good candidates for the metallic barrier. The localized corrosion phenomena, pitting and crevice corrosion, are considered as potentially limiting for the barrier lifetime. An understanding of the mechanisms of localized corrosion of how various parameters affect it will be necessary for adequate performance assessments of candidate container materials. Examples of some of the concerns involving candidate container materials. Examples of some of the concerns of involving localized corrosion are discussed. The effects of various parameters, such as temperature and concentration of halide species, on localized corrosion are given. In addition concerns about aging of the protective oxide layer in the expected service temperature range (50 to 250{degrees}C) are presented. Also some mechanistic considerations of localized corrosion are given. 31 refs., 1 tab.

Cross Reference Analysis of Fortran (Craft) is a set of programs which extract cross reference data from listing files generated by the Cray Research cft77 Fortran compiler. The data is separated into a number of files by a preprocessor written in C. These data files are sorted and then post processed by a Fortran program to generate various summary reports as requested by the user. 7 refs.

In order to significantly decrease the amount of time required to fill the cryostats, it is desired to raise the setpoint of the 'operating' relief valve on the argon storage dewar to 20 psig from its existing 16 psig setting. This additional pressure increases the flow to the cryostats and will overwhelm the relief capacity if the temperature of the modules within these vessels is warm enough. Using some conservative assumptions and simple calculations within this note, the maximum average temperature that the modules within each cryostat can be at prior to filling from the storage dewar with liquid argon is at least 290 K.

The crystal structure of stage-1 iodine-intercalated superconducting IBi{sub 2}Sr{sub 2}CaCu{sub 2}O{sub x} has been determined by transmission electron microscopy to belong to the superspace group C{sub {anti 1}1}{sub {anti 1}}{sup Pma2} with subcell lattice parameters a = 5.4 {Angstrom}, b = 5.4 {Angstrom}, c = 18.8 {Angstrom}, and a structural modulation wavelength of 26 {Angstrom}. Intercalated iodine atoms alter the atomic stacking across Bi-O layers from the staggered configuration characteristic of superconducting Bi{sub 2}Sr{sub 2}CaCu{sub 2}O{sub x} to a vertically aligned configuration in IBi{sub 2}Sr{sub 2}CaCu{sub 2}O{sub x}. From the atomic spacings apparent in the images, it is concluded that the iodine layers bond to their neighboring Bi-O layers by van der Waals interactions. 9 refs., 8 figs., 2 tabs.

As part of the environmental assessment process for the proposed modifications to the US Air Force Maui Space Surveillance Site, an archaeological survey was conducted of Science City, an observatory complex on a summit of Haleakala Mountain, Island of Maui, Hawaii. Inspection of the 3.1-ha facility revealed four archaeological sites, designated 50-11-2805 through 50-11-2808. All consist of one or more temporary, probably single-person shelters with leveled floors and walls of stacked stones. Review of the literature and discussions with state officials resulted in a finding that these sites meet the criteria for nomination to the National Register of Historic Places. Four archaeological sites were found during the archaeological survey of the land parcel known as Science City on the crest of Haleakala. Each consisted of one or more stone features known as shelters. These sites meet the criteria for eligibility to the National Register of Historic Places, under criterion (d), potential to yield important scientific information about prehistory. No evidence of any other historical use of the area was found. Two of the sites are located inside the proposed MSSS boundary but will not be physically altered by construction. Although construction will have an effect on the setting of these …

Waste slurries produced during the recovery of plutonium and uranium from irradiated fuel are stored in underground storage tanks. While a variety of waste types have been generated, of particular concern are the wastes stored in Tank 101-SY. A slurry growth-gas evolution cycle has been observed since 1981. The waste consists of a thick slurry, consisting of a solution high in NaOH, NaNO{sub 3}, NaAlO{sub 2}, dissolved organic complexants (EDTA, HEDTA, NTA, and degradation products), other salts (sulfates and phosphates), and radionuclides (primarily cesium and strontium). During a gas release the major gaseous species identified include: hydrogen and nitrous oxide (N{sub 2}O). Significant amounts of nitrogen may also be present. Traces of ammonia, carbon oxides, and other nitrogen oxides are also detected. Air and water vapor are also present in the tank vapor space. The purpose of the deflagration study is to determine risks of the hydrogen, nitrous oxide, nitrogen, and oxygen system. To be determined are pressure and temperature as a function of composition of reacting gases and the concentration of gases before and after the combustion event. Analyses of gases after the combustion event will be restricted to those tests that had an initial concentration of {le}8% hydrogen. …