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Critical Review of Glass Performance Modeling
Borosilicate glass is to be used for permanent disposal of high-level nuclear waste in a geologic repository. Mechanistic chemical models are used to predict the rate at which radionuclides will be released from the glass under repository conditions. The most successful and useful of these models link reaction path geochemical modeling programs with a glass dissolution rate law that is consistent with transition state theory. These models have been used to simulate several types of short-term laboratory tests of glass dissolution and to predict the long-term performance of the glass in a repository. Although mechanistically based, the current models are limited by a lack of unambiguous experimental support for some of their assumptions. The most severe problem of this type is the lack of an existing validated mechanism that controls long-term glass dissolution rates. Current models can be improved by performing carefully designed experiments and using the experimental results to validate the rate-controlling mechanisms implicit in the models. These models should be supported with long-term experiments to be used for model validation. The mechanistic basis of the models should be explored by using modern molecular simulations such as molecular orbital and molecular dynamics to investigate both the glass structure and its dissolution process.
ANL Technical Support Program for DOE Environmental Restoration and Waste Management
A program was established for DOE Environmental Restoration and Waste Management (EM) to evaluate factors that are anticipated to affect waste glass reaction during repository disposal, especially in an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site.
Development of a Small-Channel Nucleate-Boiling Heat Transfer Correlation
Development of an improved semi-mechanistic-based set of correlation parameters for nucleation-dominant flow-boiling heat transfer in small channels is described.
Argonne National Laboratory-East Site Environmental Report for Calendar Year 1993
This annual report on the ANL environmental protection program provides the DOE, environmental agencies, and the public with information on the levels of radioactive and chemical pollutants in the vicinity of ANL and on the amounts, if any, added to the environment by ANL operations. It also summarizes compliance of ANL operations with applicable environmental laws and regulations and highlights significant accomplishments and problems related to environmental protection. The report follows the guidelines given in DOE Order 5400.1.
First Assessment of Computations of Turbulent Bubbly Flow and Particulate Flow with the COMMIX-M Program
The COMMIX-M computer code, which describes steady-state and transient single- and multi-component flows in engineering systems, has been implemented to simulate suspension flows in laminar regimes and turbulent and bubbly particulate flows. This report presents a synopsis of the present code's capabilities, with particular emphasis on the recent development of turbulence models, and explains in detail the modifications necessary to simulate particulate flows and bubbly flows. First results of computations of turbulent bubbly and particulate flows are then given and compared with results of computations reported in the literature and with preliminary experimental results obtained at the Kernforschungszentrum Karlsruhe (Germany).
Glassy Slags for Minimum Additive Waste Stabilization: Interim Progress Report, May 1993-February 1994
Interim report describing progress to develop glassy slag waste forms that support environmental restoration efforts.
Nuclear Waste Programs Semiannual Progress Report: April-September 1992
This document reports on the work done by the Nuclear Waste Programs of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period April-September 1992. In these programs, studies are underway on the performance of waste glass and spent fuel in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.
A Parallel Genetic Algorithm for the Set Partitioning Problem
In this dissertation the author reports on his efforts to develop a parallel genetic algorithm and apply it to the solution of set partitioning problem -- a difficult combinatorial optimization problem used by many airlines as a mathematical model for flight crew scheduling. He developed a distributed steady-state genetic algorithm in conjunction with a specialized local search heuristic for solving the set partitioning problem. The genetic algorithm is based on an island model where multiple independent subpopulations each run a steady-state genetic algorithm on their subpopulation and occasionally fit strings migrate between the subpopulations. Tests on forty real-world set partitioning problems were carried out on up to 128 nodes of an IBM SP1 parallel computer. The authors found that performance, as measured by the quality of the solution found and the iteration on which it was found, improved as additional subpopulation found and the iteration on which it was found, improved as additional subpopulations were added to the computation. With larger numbers of subpopulations the genetic algorithm was regularly able to find the optimal solution to problems having up to a few thousand integer variables. In two cases, high-quality integer feasible solutions were found for problems with 36,699 and 43,749 integer variables, respectively. A notable limitation they found was the difficulty solving problems with many constraints.
Studies of Acute and Chronic Radiation Injury at the Biological and Medical Research Division, Argonne National Laboratory, 1953-1970 : Description of Individual Studies, Data Files, Codes, and Summaries of Significant Findings
Between 1953 and 1970, studies on the long-term effects of external x-ray and {gamma} irradiation on inbred and hybrid mouse stocks were carried out at the Biological and Medical Research Division, Argonne National Laboratory. The results of these studies, plus the mating, litter, and pre-experimental stock records, were routinely coded on IBM cards for statistical analysis and record maintenance.
Surveillance of Site A and Plot M : Report for 1993
The results of the environmental surveillance program conducted at Site A/Plot M in the Palos Forest Preserve area for CY 1993 are presented. The surveillance program is the ongoing remedial action that resulted from the 1976-1978 radiological characterization of the site. That study determined that very low levels of hydrogen-3 (as tritiated water) had migrated from the burial ground and were present in two nearby hand-pumped picnic wells.
Chemical Technology Division Annual Technical Report: 1993
Annual report of the Argonne National Laboratory Chemical Technology Division (CMT) discussing the group's activities during 1992. These included electrochemical technology; fossil fuel research; hazardous waste research; nuclear waste programs; separation science and technology; integral fast reactor pyrochemical processes; actinide recovery; applied physical chemistry; basic chemistry research; and analytical chemistry.
Color Measurements on Marble and Limestone Briquettes Exposed to Outdoor Environment in the Eastern United States
In a long-term program that began in 1984, limestone and marble briquettes have been exposed to both anthropogenic acid deposition and natural weathering at four field sites in the eastern United States.
Gas Generation from Hanford Grout Samples : Final Report
The radiolytic yields of hydrogen nitrogen, oxygen, nitrous oxide, and carbon monoxide from two batches of WHC-supplied samples of grouted simulated waste have been (gamma) irradiated at several dose rates (0.025, 0.63 and 130 krad/h for hydrogen and 130 krad/h for all other gases). In one batch, the liquid waste simulant that was added to the grout included the original components that were added to Tank 102-AP (labeled "virgin" waste.) The second batch included a similar liquid waste simulant that was preirradiated to 35 Mrad prior to incorporation into the grout. It is believed that the preirradiated samples more closely represent radioactive waste that was stored in the tank for several years. The lowest dose rate corresponds approximately to that expected in the grout; with the high dose rate, doses equivalent to about 85 years storage in grout vaults were achieved. Most of the results on the batch of virgin samples have been reported recently (Report ANL 93/42). Here we report the results from the batch of preirradiated grout samples and compare the results from the two batches. The radiolytic yields of hydrogen and nitrogen are lower in the preirradiated than in the virgin grout. On the other hand G(oxygen) is higher in the preirradiated samples: 0.078 vs. 0.026. The yield of nitrous oxide is essentially the same, G(nitrous oxide) = 0.010, in both. The yields measured from both batches are significantly higher than previously reported values. At 90 C similar amounts of hydrogen were generated thermally from both batches of grout, whereas the total amounts of nitrogen and nitrous oxide were larger for the preirradiated than for the virgin grout samples. At lower temperatures the rate of generation was hardly measurable. Mass spectrometric analysis suggests that NO is thermally (but not radiolytically) released from the grout samples.
Solidification Modeling of a Spiral Casting to Determine Material Fluidity
In casting, fluidity is the measure of the distance a metal can flow in a channel before being stopped by solidification. During mold filling, the metal loses heat to the surrounding mold, thereby cooling and becoming more viscous until the leading portion solidifies and no further flow is possible. A coupled heat-transfer and fluid-flow modeling of a spiral, involving the use of thermophysical properties to determine material fluidity, has been conducted. Simulations of these experiments utilized the Casting Process Simulator (CaPS) software developed at Argonne National Laboratory. Two types of spiral geometries with different assumptions were considered: (1) a two-dimensional laterally stretched spiral and (2) a three-dimensional lateral spiral. The computer extent of mold filling is in good agreement with the experimental results. Time required by the metal/gas interface to attain specific positions in the spiral arm also compares favorably with the experimental results. The influence of process variables, especially pour time, is discussed. The CaPS software has been used as a computational tool to investigate the validity of the dimensionality assumptions and to evaluate the ability of CaPS to model fluidity adequately.
Conceptual Design of a Forced-Flow-Cooled 20-kA Current Lead Using Ag-Alloy-Sheathed Bi-2223 High-Temperature Superconductors
The use of high-temperature superconductors in current leads to reduce refrigeration power has been investigated by many groups in the past.
OTTER 3.0 Reference Manual and Guide
OTTER (Organized Techniques for Theorem-proving and Effective Research) is a resolution-style theorem-proving program for first-order logic with equality. OTTER includes the inference rules binary resolution, hyperresolution, UR-resolution, and binary paramodulation. Some of its other abilities and features are conversion from first-order formulas to clauses, forward and back subsumption, factoring, weighting, answer literals, term ordering, forward and back demodulation, evaluable functions and predicates, and Knuth-Bendix completion. OTTER is coded in C, is free, and is portable to many different kinds of computer.
Separation Science and Technology Semiannual Progress Report
This document reports on the work done by the Separations Science and Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1991-March 1992. This effort is mainly concerned with developing the TRUEX process for removing and concentrating actinides from acidic waste streams contaminated with transuranic (TRU) elements. The objectives of TRUEX processing are to recover valuable TRU elements and to lower disposal costs for the nonTRU waste product of the process.
Applied Physical Chemistry Progress Report, October 1991 - September 1992
This document reports on the work done in applied physical chemistry at the Chemical Technology Division (CMT), Argonne National Laboratory (ANL), in the period October 1991 through September 1992. this work includes research into the process that control the release and transport of fission products under accident-like conditions in a light water reactor, the thermophysical properties of the metal fuel in the Integral Fast Reactor under development at ANL, and the properties of candidate tritium breeding materials in environments simulating those of fusion energy systems.
Compatibility of ITER Candidate Structural Materials with Static Gallium
Tests were conducted on the compatibility of gallium with candidate structural materials for the International Thermonuclear Experimental Reactor, e.g., Type 316 SS, Inconel 625, and Nb-5 Mo-1 Zr alloy, as well as Armco iron, Nickel 270, and pure chromium.
Effects of Radionuclide Decay on Waste Glass Behavior : a Critical Review
This paper is an extension of a chapter in an earlier report that provides an updated review on the status of radiation damage problems in nuclear waste glasses. This report will focus on radiation effects on vitrified borosilicate nuclear waste glasses under conditions expected in the proposed Yucca mountain repository. Radiation effects on high-level waste glasses and their surrounding repository environment are important considerations for radionuclide immobilization because of the potential to alter the glass stability and thereby influence the radionuclide retentive properties of this waste form. The influence of radionuclide decay on vitrified nuclear waste may be manifested by several changes, including volume, stored energy, structure, microstructure, mechanical properties, and phase separation. Radiation may also affect the composition of aqueous fluids and atmospheric gases in relatively close proximity to the waste form. What is important to the radionuclide retentive properties of the repository is how these radiation effects collectively or individually influence the durability and radionuclide release from the glass in the event of liquid water contact.
Periodized Wavelets
The properties of periodized Daubechies wavelets on [0,1] are detailed and contrasted against their counterparts which form a basis for L{sup 2}(R). Numerical examples illustrate the analytical estimates for convergence and demonstrate by comparison with Fourier spectral methods the superiority of wavelet projection methods for approximations. The analytical solution to inner products of periodized wavelets and their derivatives, which are known as connection coefficients, is presented, and several tabulated values are included.
Early Experiences with the IBM SP1 and the High-Performance Switch
The IBM SP1 is IBM`s newest parallel distributed-memory computer. As part of a joint project with IBM, Argonne took delivery of an early system in order to evaluate the software environment and to begin porting programming packages and applications to this machine. This report discusses the results of those efforts once the high-performance switch was installed. An earlier report (ANL/MCS-TM-177) emphasized software usability and the initial ports to the SP1. This report contains performance results and discusses some applications and tools not covered in TM 177.
Nuclear Waste Programs Semiannual Progress Report: October 1991-March 1992
This document reports on the work done by the Nuclear Waste Programs of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period October 1991-March 1992. In these programs, studies are underway on the performance of waste glass and spent fuel in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.
On the Unsteady-Motion Theory of Magnetic Forces for Maglev
Motion-dependent magnetic forces are the key elements in the study of magnetically levitated vehicle (maglev) system dynamics. In the past, most maglevsystem designs were based on a quasisteady-motion theory of magnetic forces. This report presents an experimental and analytical study that will enhance our understanding of the role of unsteady-motion-dependent magnetic forces and demonstrate an experimental technique that can be used to measure those unsteady magnetic forces directly. The experimental technique provides a useful tool to measure motion-dependent magnetic forces for the prediction and control of maglev systems.
Using a Transfer Function to Describe the Load-Balancing Problem
The dynamic load-balancing problem for mesh-connected parallel computers can be clearly described by introducing a function that identifies how much work is to be transmitted between neighboring processors. This function is a solution to an elliptic problem for which a wealth of knowledge exists. The non-uniqueness of the solution to the load-balancing problem is made explicit.
Practical Superconductor Development for Electrical Power Applications, Annual Report: 1993
Annual report for the superconductor program at Argonne National Laboratory discussing the group's activities and research. This report describes technical progress of research and development efforts aimed at producing superconducting components in the Y-Ba-Cu, (B1,Pb)-Sr-Ca-Cu, (Tl,Pb,BI)-(Ba,Sr)-Ca-Cu, and Hg-Ba-Ca-Cu-O oxide systems including: synthesis and heat treatment of high-Ta superconductors; formation of monolithic and composite wires, tapes, and coils; characterization of structures and superconducting and mechanical properties; fabrication and properties of films; and development of prototype components.
Programming in Fortran M Revision 1
Fortran M is a small set of extensions to Fortran that supports a modular approach to the construction of sequential and parallel programs. Fortran M programs use channels to plug together processes which may be written in Fortran M or Fortran 77. Processes communicate by sending and receiving messages on channels. Channels and processes can be created dynamically, but programs remain deterministic unless specialized nondeterministic constructs are used. Fortran M programs can execute on a range of sequential, parallel, and networked computers. This report incorporates both a tutorial introduction to Fortran M and a users guide for the Fortran M compiler developed at Argonne National Laboratory. The Fortran M compiler, supporting software, and documentation are made available free of charge by Argonne National Laboratory, but are protected by a copyright which places certain restrictions on how they may be redistributed. See the software for details. The latest version of both the compiler and this manual can be obtained by anonymous ftp from Argonne National Laboratory in the directory pub/fortran-m at info.mcs.anl.gov.
Radiolytic and Radiolytically Induced Generation of Gases from Synthetic Wastes : Final Report
To better understand the processes leading to the generation and release of gases from waste tanks, the authors studied the radiolytic and thermal generation of H2, N2O, N2, O2, and NH3 in nonradioactive waste simulant solutions and slurries. The radiolytic sources for H2 are e(sub aq)⁻ and its predecessors and H atoms. Radiolysis of the water generates some H2 and an additional amount comes from the hydrogen abstraction reaction H + RH(yields) H2+R(center_dot). Nitrate scavenges e(sub aq)(sup (minus) and its predecessors whereas nitrite is the major H-atom scavenger. Computer modeling shows that if [NO3⁻] is above 0.5 M, and [NO2⁻] is above 2M, the addition of other scavengers will have little effect on the yield of H2. In the presence of organic molecules O2 is efficiently destroyed. Small yields of ammonia were measured and the yields increase linearly with dose. The nitrogen in NH3 comes from organic chelators. The yields of gases in solution depend only weakly on temperature. The rate of thermal generation of gases increases upon preirradiation, reaches a maximum, and then declines. The known radiolytic degradation products of chelators, NTA, IDA, glycolate, glyoxylate, formaldehyde, formate, oxalate, and hydroxylainine were examined for their roles in the thermal generation of H2 and N2O at 60 C. In solution or slurry only radiolytically produced Pd intermediate strongly retains H2. Radiolytic yields of N2O are strongly reduced by Cr(III). In irradiated slurry, loose and tight gas were found. The loose gas could be removed by bubbling from the slurry, but the tight gas could be released only by dissolution of the slurry.
Radiolytic and Thermal Generation of Gases from Hanford Grout Samples : Interim Report
Gamma irradiation of WHC-supplied samples of grouted Tank 102-AP simulated nonradioactive waste has been carried out at three dose rates, 0.25, 0.63, and 130 krad/hr. The low dose rate corresponds to that in the actual grout vaults; with the high dose rate, doses equivalent to more than 40 years in the grout vault were achieved. An average G(H2) = 0.047 molecules/100 eV was found, independent of dose rate. The rate of H2 production decreases above 80 Mrad. For other gases, G(N2) = 0.12, G(O2) = 0.026, G(N2O) = 0.011 and G(CO) = 0.0042 at 130 krad/hr were determined. At lower dose rates, N2 and O2 could not be measured because of interference by trapped air. The value of G(H2) is higher than expected, suggesting segregation of water from nitrate and nitrite salts in the grout. The total pressure generated by the radiolysis at 130 krad/h has been independently measured, and total amounts of gases generated were calculated from this measurement. Good agreement between this measurement and the sum of all the gases that were independently determined was obtained. Therefore, the individual gas measurements account for most of the major components that are generated by the radiolysis. At 90 C, H2, N2, and N2O were generated at a rate that could be described by exponential formation of each of the gases. Gases measured at the lower temperatures were probably residual trapped gases. An as yet unknown product interfered with oxygen determinations at temperatures above ambient. The thermal results do not affect the radiolytic findings.
Fortran M Language Definition
This document defines the Fortran M extensions to Fortran 77. It updates an earlier definition, dated June 1992, in several minor respects.
Physics Division Annual Review: April 1, 1992-March 31, 1993
Annual report of activities of the Argonne National Laboratory Physics Division, including heavy-ion research, operation and development of ATLAS, medium-energy nuclear physics research and weak interactions, theoretical nuclear physics, and atomic and molecular physics research.
Programming in Fortran M
Fortran M is a small set of extensions to Fortran that supports a modular approach to the construction of sequential and parallel programs. Fortran M programs use channels to plug together processes which may be written in Fortran M or Fortran 77. Processes communicate by sending and receiving messages on channels. Channels and processes can be created dynamically, but programs remain deterministic unless specialized nondeterministic constructs are used. Fortran M programs can execute on a range of sequential, parallel, and networked computers. This report incorporates both a tutorial introduction to Fortran M and a users guide for the Fortran M compiler developed at Argonne National Laboratory. The Fortran M compiler, supporting software, and documentation are made available free of charge by Argonne National Laboratory, but are protected by a copyright which places certain restrictions on how they may be redistributed. See the software for details. The latest version of both the compiler and this manual can be obtained by anonymous ftp from Argonne National Laboratory in the directory pub/fortran-m at info.mcs.anl.gov.
Ion Replacement Program Annual Report: 1993
Annual report of the Ion Replacement Electrorefining Program at Aronne National Laboratory describing their research and activities. There are three key accomplishments highlighted for the year: (1) identification of a suitable sodium(beta){double_prime}-alumina/molten salt electrolyte system that functions reproducibly at 723 K, (2) actual separation of dysprosium and lanthanum in experiments, and (3) the identification of a metal alloy, Li{sub x}Sb, as an alternative ion replacement electrode.
Nuclear Technology Programs Semiannual Progress Report: April-September 1991
Progress report of the Argonne National Laboratory's Nuclear Technology Programs, including R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management.
User`s Guide for the Casting Process Simulator Software CaPS-2D, Version 1.0
Most casting defects occur during initial pouring and therefore the design of the running system, which guides the metal from the ladle into the mold, is crucial. Traditionally, the running system and mold filling are designed by trial and error, which is tedious, time consuming, and expensive. The uncertainties that remain can be overcome by a computer simulation that demonstrates the actual process of mold filling and subsequent solidification. Computer simulation of various processes has become more and more common in recent years. The cost-effectiveness of making flawless castings has made the foundry worker more aware of the process of mold filling, identification of hot spots, etc. The macroscopic Casting Process Simulator (CaPS) software combines heat transfer and fluid flow aspects and can describe a variety of solidification aspects, including mold filling. CaPS is a two-dimensional time-dependent computer code involving a finite-volume formulation for the mass, momentum. and energy equations. CaPS has the following characteristics. CaPS uses the PATRAN geometric modeling package for constructing the geometry, generating a neutral file consisting of a list of named components, and post-processing of the simulation results; building the geometry independently of the mesh is a time-saving procedure. A structured mesh generator of structured regular cells is included and is interfaced with the neutral-file output of the solid geometric package. Visual user interfaces have been developed on the basis of the HOOPS package, which contains a hierarchical database of geometric information. The CaPS shell scripts interactively provide a step-by-step procedure to simulate the solidification process, thus making the software very user-friendly.
Chemical Technology Division Annual Technical Report: 1992
Annual report of the Argonne National Laboratory Chemical Technology Division (CMT) discussing the group's activities during 1992. These included electrochemical technology; fossil fuel research; hazardous waste research; nuclear waste programs; separation science and technology; integral fast reactor pyrochemical processes; actinide recovery; applied physical chemistry; basic chemistry research; analytical chemistry; applied research and development; and computer applications.
Experiment on Fluidelastic Instability of Loosely Supported Tube Arrays in Crossflow
A tube array supported by baffle plates in crossflow may be subjected to fluid-elastic instability in the tube-support-plate-inactive mode. An experimental study is presented to characterize the tube motion. Three series of tests were performed to measure tube displacements as a function of flow velocity for different clearances. The motion was examined by root-mean-square values of tube displacements, power spectral densities, phase planes, Poincare maps, and Lyapunov exponents. The experimental data agree reasonably well with the analytical model, based on the unsteady flow theory.
Motion-Dependent Fluid Forces Acting on Tube Arrays in Crossflow
Motion-dependent fluids forces acting on a tube array were measured as a function of excitation frequency, excitation amplitude, and flow velocity. Fluid-damping and fluid-stiffness coefficients were obtained from measured motion-dependent fluid forces as a function of reduced flow velocity and excitation amplitude. The water channel and test setup provide a sound facility for obtaining key coefficients for fluid-elastic instability of tube arrays in crossflow. Once the guideline, based on the unsteady flow theory, can be developed for fluid-elastic instability of tube arrays crossflow.
Preliminary Plan for Treating Mixed Waste
A preliminary waste treatment plan was developed for disposing of radioactive inorganic liquid wastes that contain hazardous metals and/or hazardous acid concentrations at Argonne National Laboratory. This plan, which involves neutralization and sulfide precipitation followed by filtration, reduces the concentration of hazardous metals and the acidity so that the filtrate liquid is simply a low-level radioactive waste that can be fed to a low-level waste evaporator.
Users manual for the Chameleon Parallel Programming Tools
Message passing is a common method for writing programs for distributed-memory parallel computers. Unfortunately, the lack of a standard for message passing has hampered the construction of portable and efficient parallel programs. In an attempt to remedy this problem, a number of groups have developed their own message-passing systems, each with its own strengths and weaknesses. Chameleon is a second-generation system of this type. Rather than replacing these existing systems, Chameleon is meant to supplement them by providing a uniform way to access many of these systems. Chameleon`s goals are to (a) be very lightweight (low over-head), (b) be highly portable, and (c) help standardize program startup and the use of emerging message-passing operations such as collective operations on subsets of processors. Chameleon also provides a way to port programs written using PICL or Intel NX message passing to other systems, including collections of workstations. Chameleon is tracking the Message-Passing Interface (MPI) draft standard and will provide both an MPI implementation and an MPI transport layer. Chameleon provides support for heterogeneous computing by using p4 and PVM. Chameleon`s support for homogeneous computing includes the portable libraries p4, PICL, and PVM and vendor-specific implementation for Intel NX, IBM EUI (SP-1), and Thinking Machines CMMD (CM-5). Support for Ncube and PVM 3.x is also under development.
7-GeV Advanced Photon Source Beamline Initiative. Conceptual Design Report
The DOE is building a new generation 6-7 GeV Synchrotron Radiation Source known as the Advanced Photon Source (APS) at Argonne National Laboratory. This facility, to be completed in FY 1996, can provide 70 x-ray sources of unprecedented brightness to meet the research needs of virtually all scientific disciplines and numerous technologies. The technological research capability of the APS in the areas of energy, communications and health will enable a new partnership between the DOE and US industry. Current funding for the APS will complete the current phase of construction so that scientists can begin their applications in FY 1996. Comprehensive utilization of the unique properties of APS beams will enable cutting-edge research not currently possible. It is now appropriate to plan to construct additional radiation sources and beamline standard components to meet the excess demands of the APS users. In this APS Beamline Initiative, 2.5-m-long insertion-device x-ray sources will be built on four straight sections of the APS storage ring, and an additional four bending-magnet sources will also be put in use. The front ends for these eight x-ray sources will be built to contain and safeguard access to these bright x-ray beams. In addition, funds will be provided to build standard beamline components to meet scientific and technological research demands of the Collaborative Access Teams. The Conceptual Design Report (CDR) for the APS Beamline Initiative describes the scope of all the above technical and conventional construction and provides a detailed cost and schedule for these activities. The document also describes the preconstruction R & D plans for the Beamline Initiative activities and provides the cost estimates for the required R & D.
ANL Technical Support Program for DOE Environmental Restoration and Waste Management Annual Report for October 1991 - September 1992
Management (EM) to evaluate factors that are anticipated to affect waste glass reaction during repository disposal, especially in an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site.
Argonne National Laboratory-East Site Environmental Report for Calendar Year 1992
This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1992. To evaluate the effects of ANL operations .on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples.
Surveillance of Site A and Plot M : Report for 1992
The results of the environmental surveillance program conducted at Site A/Plot M in the Palos Forest Preserve area for CY 1992 are presented. The surveillance program is the ongoing remedial action that resulted from the 1976-1978 radiological characterization of the site. That study determined that very low levels of hydrogen-3 (as tritiated water) had migrated from the burial ground and were present in two nearby hand-pumped picnic wells. The current program consists of sample collection and analysis of air, surface and subsurface water, and bottom sediment.
BlockSolve v1. 1: Scalable Library Software for the Parallel Solution of Sparse Linear Systems
BlockSolve is a software library for solving large, sparse systems of linear equations on massively parallel computers. The matrices must be symmetric, but may have an arbitrary sparsity structure. BlockSolve is a portable package that is compatible with several different message-passing pardigms. This report gives detailed instructions on the use of BlockSolve in applications programs.
Lead Exposures and Biological Responses in Military Weapons Systems: Aerosol Characteristics and Acute Lead Effects among US Army Artillerymen: Final Report
This study was to determine the concentration and chemical nature of lead (Pb) aerosols produced during the firing of artillery and to determine the exposures and biological responses of crew members exposed to lead aerosols during such firing. The concentrations of lead-containing aerosols at crew positions depended on wind conditions, with higher concentrations when firing into a head wind. Aerosol concentrations were highest in the muzzle blast zone. Concentrations of lead in the blood of crew members rose during the first 12 days of exposure to elevated airborne lead concentrations and then leveled off. There was no rapid decrease in blood lead concentrations after completion of firing. Small decreases in hematocrit and small increases in free erythrocyte porphyrin were correlated with increasing exposure to airborne lead. These changes were reversed by seven weeks after firing. Changes in nerve conduction velocity had borderline statistical significance to airborne lead exposure. In measuring nerve conduction velocity, differences in skin temperature must be taken into account.
COMMIX-PPC: A Three-Dimensional Transient Multicomponent Computer Program for Analyzing Performance of Power Plant Condensers, Volume 1: Equations and Numerics
Report on the COMMIX-PPC computer program, designed to evaluate the thermal performance of power plant condensers. This first volume "describes in detail the basic equations, formulation, solution procedures, and models for auxiliary phenomena" (p. iv).
Simplified Linear Equation Solvers : Users Manual
The solution of large sparse systems of linear equations is at the heart of many algorithms in scientific computing. The SLES package is a set of easy-to-use yet powerful and extensible routines for solving large sparse linear systems. The design of the package allows new techniques to be used in existing applications without any source code changes in the applications.
Nondestructive Characterization Methods for Monolithic Solid Oxide Fuel Cells
Monolithic solid oxide fuel cells (MSOFCS) represent a potential breakthrough in fuel cell technology, provided that reliable fabrication methods can be developed. Fabrication difficulties arise in several steps of the processing: First is the fabrication of uniform thin (305 {mu}m) single-layer and trilayer green tapes (the trilayer tapes of anode/electrolyte/cathode and anode/interconnect/cathode must have similar coefficients of thermal expansion to sinter uniformly and to have the necessary electrochemical properties); Second is the development of fuel and oxidant channels in which residual stresses are likely to develop in the tapes; Third is the fabrication of a "complete" cell for which the bond quality between layers and the quality of the trilayers must be established; and Last, attachment of fuel and oxidant manifolds and verification of seal integrity. The purpose of this report is to assess nondestructive characterization methods that could be developed for application to laboratory, prototype, and full-scale MSOFCs.
Parallel Programming with PCN. Revision 2
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. It includes both tutorial and reference material. It also presents the basic concepts that underlie 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. This version of this document describes PCN version 2.0, a major revision of the PCN programming system. It supersedes earlier versions of this report.
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