Report on experiments to assess the importance of radiation effects on waste glass corrosion. This third part contains a description of the experiments, results, and discussion, with conclusions and related appendices.

Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes efforts on development of molten carbonate fuel cells directed toward seeking alternative cathode materials to NiO. Based on an investigation of the thermodynamically stable phases formed under cathode conditions with a number of transition metal oxides, synthesis of prospective alternative cathode materials and doping of these materials to promote electronic conductivity is under way.

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.

Annual report of the Solar Energy Program describing work in solar energy collection, heating and cooling, thermal energy storage, ocean thermal energy conversion, photovoltaics, satellite power systems, bioconversion, central receiver solar thermal power, and wind energy conversion.

Nuclear material inventory verification techniques for large split-table type fast critical assemblies are being studied under this program. Emphasis has been given to techniques that minimize fuel handling in order to reduce facility down time and radiation exposure to the inventory team. The techniques studied include autoradiography, reactivity, and spectral index measurements.

The objective of this study was to assess the health and environmental impacts of fluidized-bed combustion of coal (FBC), specifically as applied to base-load generation of electrical energy by utilities. The public health impacts of Fluidized-Bed Combustion (FBC) plants are expected to be quite similar to those for Low Sulfur Coal (LSC) and Flue Gas Desulfurization (FGD) plants because all appear to be able to meet Federal emission standards; however, there are emissions not covered by standards. Hydrocarbon emissions are higher and trace element emissions are lower for FBC than for conventional technologies. For FBC, based on an analytical model and a single emission data point, the polycyclic organic material decreases the anticipated lifespan of the highly exposed public very slightly. Added health protection due to lower trace element emissions is not known. Although there is a large quantity of solid wastes from the generating plant, the environmental impact of the FBC technology due to solid residue appears lower than for FGD, where sludge management requires larger land areas and presents problems due to the environmentally noxious calcium sulfite in the waste. Fixing the sludge may become a requirement that increases the cost of wet-limestone FGD but makes that system …

From introduction: "The report is preliminary. At the time of writing, the status of the BORAX V project is that design of the reactor buildings and plant, done in collaboration with the architect-engineer with the architect-engineer has been completed and construction has just started; however, the mechanical design of the fuel and cores is still tentative."

Report on studies of advanced batteries, aqueous batteries, advanced fuel cells, coal utilization, methodologies for recovery of energy from municipal waste, solid and liquid desiccants, nuclear technology related to waste management, and physical chemistry of selected materials in environments simulating those of fission, fusion, and other energy systems.

Annual report for the superconductor program at Argonne National Laboratory discussing the group's activities and research. This report documents research efforts aimed at producing superconducting components based on oxide systems.

Report issued by the Argonne National Laboratory discussing a summary report of work completed between April and October, 1958. Summaries of the studies conducted and work completed are presented. This report includes tables, and illustrations.

The report is the third in a series of interim reports on the climatological studies which are being conducted at the Argonne National Laboratory. First report appeared as document ANL-4538 and covered the period July, 1949 through June, 1950; the second report, ANL-4793, covered the period July, 1950 through June, 1951. These annual reports are offered for purposes of information only; broad conclusions regarding the climate of this site must await the accumulation of a statistically significant amount of data.

This report covers the research, development, and management activities of the programs involving high-performance lithium-aluminum/iron sulfide batteries at Argonne National Laboratory (ANL) and at contractors' laboratories during the period October 1979 through September 1980. These batteries, which are being developed for electric-vehicle propulsion and stationary energy storage applications, consist of vertically oriented prismatic cells with one or more inner positive electrodes of FeS or FeS2 facing negative electrodes of lithium-aluminum, and molten LiCl-KCl electrolyte.

This report covers the research, development, and management activities of the programs involving high-performance lithium-aluminum/iron sulfide batteries at Argonne National Laboratory (ANL) and at contractors' laboratories during the period October 1980 through September 1981. These batteries, which are being developed for electric-vehicle propulsion and stationary energy-storage applications, consist of vertically oriented prismatic cells with one or more inner positive electrodes of FeS or FeS2, facing negative electrodes of lithium-aluminum, and molten LiCl-KC1 electrolyte.

The application of neutron activation analysis to the determination of element release from simulated nuclear waste forms during leaching is described for several different glasses. Potential neutron irradiation effects are discussed, and it is shown, by a series of leach tests on activated and non-activated glass samples, that neutron irradiation has no discernible effect on the release of silicon and cesium during leaching. The radioisotopes best suited for analysis with this method and their associated detection limits are identified, and the method's applicability to waste forms other than glass is discussed.

This document reports on the work done by the Nuclear Waste Management Section of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period October 1993-September 1994. Studies have been performed to evaluate the performance of nuclear waste glass and spent fuel samples under unsaturated conditions (low volume water contact) that are likely to exist in the Yucca Mountain environment being considered as a potential site for a high-level waste repository. Tests with simulated waste glasses have been in progress for over eight years and demonstrate that actinides from initially fresh glass surfaces will be released as a result of the spallation of reacted glass layers from the surface, as the small volume of water passes over the waste form.

The influence of gamma irradiation on the reaction of actinide-doped borosilicate glass (SRL 165) in a saturated tuff environment has been studied in a series of tests lasting up to 56 days. The following conclusions were reached. The reaction of, and subsequent actinide release from, the glass depends on the dynamic interaction between radiolysis effects, which cause the solution pH to become more acidic; glass reaction, which drives the pH more basic; and test component interactions that may extract glass components from solution. The use of large gamma irradiation dose rates to accelerate reactions that may occur in an actual repository radiation field may affect this dynamic balance by unduly influencing the mechanism of the glass-water reaction. Comparisons between the present results and data obtained by reacting similar glasses using MCC-1 and NNWSI rock cup procedures indicate that the irradiation conditions used in the present experiments do not dramatically influence the reaction rate of the glass.

From Abstract: "Investigations were made of alternate methods of bonding fuel shapes and the use of alternate core alloys in flat plates. Alternations and additions were made to development facilities needed to fabricate roll-clad plates for the EBWR core. Pilot production of EWBR-type plates proved that the plate cladding process could be adapted to production facilities."

The objective of the proposed Argonne Tandem-Linac Accelerator System (ATLAS) is to provide precision beams of heavy ions for nuclear physics research in the region of projectile energies comparable to nuclear binding energies (5-25 MeV/A). By using the demonstrated potential of superconducting radiofrequency technology, beams of exceptional quality and flexibility can be obtained. The system is designed to provide beams with tandem-like energy resolution and ease of energy variation, the energy range is comparable to that of approximately 50 MV tandem and, in addition, the beam will be bunched into very short (approximately 50 psec) pulses, permitting fast-timing measurements that can open up major new experimental approaches.

In the 7-GeV Advanced Photon Source (APS) Conceptual Design Report (CDR), fifteen complete experimental beam lines were specified in order to establish a representative technical and cost base for the components involved. In order to optimize the composition of the insertion devices and the beam line, these funds are considered a ''Trust Fund.'' The present report evaluates the optimization for the distribution of these funds so that the short- and long-term research programs will be most productive, making the facility more attractive from the user's point of view. It is recommended that part of the "Trust Fund" be used for the construction of the insertion devices, the front-end components, and the first-optics, minimizing the cost to potential users of completing a beam line. In addition, the possibility of cost savings resulting from replication and standardization of high multiplicity components (such as IDs, front ends, and first-optics instrumentation) is addressed.

The calorimetric instrumentation developed at Argonne National Laboratory (ANL) for making nondestructive measurements of the plutonium content of fuel rods is discussed. Measurements with these instruments are relatively fast (i.e., 15 to 20 minutes) when compared to the several hours usually required with more conventional calorimeters and for this reason are called ''fast-response.'' Most of the discussion concerns the One-Meter and the Four-Meter Fuel-Rod Calorimeters and the Analytical Small-Sample Calorimeter. However, to provide some background and continuity where needed, a small amount of discussion is devoted to the three earlier calorimeters which have been described previously in the literature. A brief review is presented of the literature on plutonium holdup measurements. The use of gamma-ray techniques for holdup measurements is discussed and results are given for the determination of sample thickness using the ratio of intensities of high- and low-energy gamma rays. The measurements cover the plutonium metal thickness range from 0.001 to 0.120 inches. The design of a gamma-ray collimator with 37 parallel holes is also discussed. Neutron-counting experiments using BF3 proportional counters embedded in two polyethylene slabs are described. This detector configuration is characterized for its sensitivity to sample and background plutonium, counting both coincidence (fission) and total …

By means of the unsteady-flow theory and a bilinear mathematical model, a theoretical study is presented for chaotic vibrations associated with the fluid-elastic instability of nonlinearly supported tubes in a crossflow. Effective tools, including phase portraits, power spectral density, Poincare maps, Lyapunov exponent, fractal dimension, and bifurcation diagrams, are utilized to distinguish periodic and chaotic motions when the tubes vibrate in the instability region. The results show periodic and chaotic motions in the region corresponding to fluid-damping-controlled instability. Nonlinear supports, with symmetric or asymmetric gaps, significantly affect the distribution of periodic, quasi-periodic, and chaotic motions of a tube exposed to various flow velocities in the instability region of the tube-support-plate-inactive mode.

This technical report is being written to document and explain some of the insights the authors have gained during the implementation of two OR-parallel Prolog systems for shared-memory multiprocessors. We have been quite amazed by how much power and functionality can be achieved through the implementation of just a few primitive predicates. We introduce a few relatively trivial predicates which allow one to implement versions of findall/3, bagof/3, and setof/3 for the a multiprocessor environment. Then we show how these predicates can be used to implement AND-parallelism. Finally, we illustrate their use for implementing a limited notion of streams, and how such streams can be used to create a compiler that achieves excellent speedups for multiprocessors with a limited number of processors.

Report of the correlations between experimental transition energies and computed level structures.

The fraction of delayed neutrons beta in slow-neutron beams from a uranium-238 pulsed spallation neutron source is 0.0053 for 300 MeV protons. This measurement appears to be the first one of this quantity. The result indicates that, for most classes of measurements, the delayed-neutron background in time-of-flight instruments will be unimportant, and places constraints on the physics description of spallation targets. The measurement was performed at the prototype pulsed spallation neutron source, ZING-P', at Argonne National laboratory.