The Nevada Nuclear Waste Storage Investigations (NNWSI) project is investigating the volcanic tuff beds of Yucca Mountain, Nevada, as a potential location for a high-level radioactive waste repository. This report describes a test method (Phase II) that has been developed to measure the release of radionuclides from the waste package under simulated repository conditions, and provides information on materials interactions that may occur in the repository. The results of 13 weeks of testing using the method are presented, and an analog test is described that investigates the relationship between the test method and expected repository conditions.

Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes activitiesdirected toward seeking alternative cathode materials to NiO for molten carbonate fuel cells.

Quarterly report on activities of Argonne National Laboratory's Nuclear Technical Programs, including management of nuclear waste.

This report describes logic programming approaches to two graph theoretical problems relevant to reactor and logic circuit analysis: those of cut-set verification and subsystem detection.

This paper surveys work recently done at Argonne National Laboratory in an attempt to discover ways to construct numerical software for high-performance computers. The numerical algorithms are taken from several areas of numerical linear algebra. Discussion of certain architectural features of advanced-computer architectures that will affect the design of algorithms. The technique of restructuring algorithms in terms of certain modules is reviewed. This technique has proved successful in obtaining a high level of transportability without severe loss of performance on a wide variety of both vector and parallel computers.

Variations in the design of a specific slip joint separating two cantilevered, telescoping tubes conveying water were studied to determine their effect upon the leakage flow-induced vibration self-excitation mechanism known to exist for the original slip joint geometry. The important parameters controlling the self-excitation mechanism were identified, which, along with previous results, allowed the determination of a comprehensive set of design rules to avoid unstable vibrations. This was possible even though a new self-excitation mechanism was found when the engagement of the two tubes was small.

The basic equations underlying a computer code are developed to describe the thermodynamic behavior of multi-component working fluids in Rankine cycles. The code is to be employed in the performance analysis of Rankine bottoming cycle systems. The performance of such systems depends strongly on the working fluid characteristics. The introduction of multi-component mixtures makes available a broad spectrum of fluid properties achievable by varying the mixture composition. The code provides a tool to analytically vary the mixture composition to optimize cycle performance.

The corrosion behavior of aluminum, copper, and iron in inhibited ethylene glycol-ASTM corrosive water solutions was evaluated in a laboratory loop under isothermal and heat-flux conditions for 1000 h at temperatures between 378 and 413 degrees K, in static autoclave tests at 450 degrees K for 500 h, and by potentiodynamic polarization measurements at temperatures between 298 and 348 degrees K. The effect of time, temperature, and ethylene glycol concentration of the heat-transfer fluid on the extent of inhibitor depletion was determined from analyses of the reserve alkalinity, pH, and inhibitor content of the solutions. The performance of an electrochemical sensor as a monitor of fluid quality was also evaluated. A heat flux of 0.4 to 1.0 kW/m sq. did not have a significant effect on the corrosion behavior of the various materials at temperatures between 378 and 413 degrees K. The corrosion rates of aluminum, copper, and iron in the 50 volume percent inhibited ethylene glycol-corrosive water solution decreased as a function of time during the 1000-h test. At 413 degrees K, the corrosion rate of copper was considerably higher than that of iron or aluminum at low flow velocity. Significant degradation of the fluid quality, as indicated by …

SACO is a fast-running computer code that simulates hypothetical accidents in liquid-metal fast breeder reactors to the point of permanent subcriticality or to the initiation of a prompt-critical excursion. In the tradition of the SAS codes each sub-assembly is modeled by a representative fuel pin with three distinct axial regions to simulate the blanket and core regions. However, analytic and integral models are used wherever possible to cut down the computing time and storage requirements. The physical models and basic equations are described in detail.

Large-scale efforts are in progress to develop advanced batteries for utility energy storage systems. Realization of the full benefits available from those systems requires development, not only of the batteries themselves, but also the ac/dc power converter, the bulk power interconnecting equipment, and the peripheral electric balance of plant equipment that integrate the battery/converter into a properly controlled and protected energy system. This study addresses these overall system aspects; although tailored to a 20-MW, 100-MWh lithium/sulfide battery system, the technology and concepts are applicable to any battery energy storage system.

Representatives of the Laboratories of the International Collaboration on Advanced Neutron Sources gathered between 28 June and 2 July, 1982 at Argonne National Laboratory for their sixth meeting, ICANS-VI. The meeting was the first opportunity for participants to see Argonne's Intense Pulsed Neutron Source, which went into full operation in August, 1981, and in an important sense celebrated the coming-on-line of this most recent entry into the world's complement of the new generation of neutron sources. The main topics of the meeting were "Targets and Moderators" and "Neutron Scattering Instrumentation", following what has become the customary rotation of subjects. An additional topic, "Nuclear Data and Codes" emerged this time as a separate entity, closely related to the Targets and Moderators subjects. These Proceedings are organized roughly in the order and organization of presentations. In addition, a record of some of the discussions is included following each Status Report, and separate summaries of discussions on various subjects of the topical sessions. The manuscripts have been reproduced essentially as received.

This is the second report describing an ongoing environmental surveillance program conducted at the Palos Park Forest Preserve near Chicago, Illinois. The Preserve was a site of a nuclear research laboratory (Site A) from 1943 to 1956 and a radioactive waste burial site (Plot M) from 1944 to 1949. An extensive radiological characterization of the site was conducted from February 1976 to August 1977, and tritium in the form of water was found to be the only radionuclide that migrated from the nuclear facilities. The results were published in US Department of Energy Report DOE/EV-0005/7. The present report summarizes the earlier findings and gives the detailed results of the work from August 1977 through December 1981. The vertical and horizontal distribution of tritium within the glacial till was determined from measurements of tritium in soil moisture. Chemical and radiochemical analyses were performed on a number of wells in the area. Tritiated water continued to be the only species that was observed to have migrated from the Plot M area. Migration from the Site A area was not observed. The concentration of tritium at the Red Gate Woods well, 1200 ft down-gradient from Plot M, continued to show the seasonal fluctuations …

The shellside pressure drop between the inlet and outlet nozzles as well as the pressure drops through individual sections of different shell-and-tube test-exchanger configurations are measured under water flow. The segmentally baffled test exchanger is nominally 0.6 m (2 ft) in diameter, 3.7 m (12 ft) long and contains a tube bundle of 19 mm (0.75 in.) outside-diameter tubes. Results are reported of 24 test cases obtained from various combinations of parameters: 30 degrees triangular or 90 degrees square tube layout patterns (all on a 1.25 pitch-to-diameter ratio), numbers of cross-passes, sizes of nozzles, plain or finned tubes, and full or special fix tube bundles. The exponential change of pressure drop as a function of flow-rate is also investigated and an attempt is made to calculate nozzle losses.

An accelerator group was established at ANL by the request of KFA-Juelich to carry out a conceptual design study and cost estimate for a rapid-cycling synchrotron as a possible first stage program on spallation neutron sources at KFA-Juelich. This set of notes is the individual notes which form the basis of the final report under this proposal prepared in January 1983. This document contains 37 papers/notes for Advanced Accelerator Development - Neutron Source Series Notes...numbered AAD-N-1 through AAD-N-37. Each note or paper is written by various authors.

Compiled proceedings of the fifth Symposium on Instrumentation and Control for Fossil-Energy Processes, covering process control involved in the conversion of fossil fuels into synthetic fuels.

A procedure was developed for separating rubidium from irradiated aluminum encapsulated uranium. The separations procedure produces a final ultra-high purity rubidium chloride product for subsequent high performance mass spectrometric analysis. The procedure involves first removing most of the macro-components and fission products by strong base anion exchange using, first, concentrated HCl, then oxalic acid media and second, selectively separating rubidium from alkaline-earth ions and other alkali-metal ions, including cesium, using Bio-Rex-40 cation-exchange resin. The resultant rubidium chloride is then put through a final vacuum sublimation step. Ultra-pure reagents and specially clean glassware are used throughout the procedure to minimize contamination by naturally-occurring rubidium.

This paper describes a computational method for improving the accuracy of a given singular value and its associated left and right singular vectors. The method is analogous to iterative improvement for the solution of linear systems. That is, by means of a low-precision computation, an iterative algorithm is applied to increase the accuracy of the singular value and vectors; extended precision computations are used in the residual calculation. The method is related to Newton's Method applied to the singular value problem and inverse iteration for the eigenvalue problem.

The Review Panel on Neutron Scattering has recommended an expanded budget to allow systematic development of the field. An alternative plan for the future of neutron research on condensed matter is presented here, in case it is not possible to fund the expanded budget. This plan leads, in a rational and logical way, to a world-class neutron source that will ensure the vitality of the field and exploit the many benefits that state-of-the-art neutron facilities can bring to programs in the materials and biological sciences.

This report is an almost verbatim copy of lectures on Electron Scattering given at Argonne National Laboratory in the Fall of 1982 by John Dirk Walecka. Professor Walecka was an Argonne Fellow in the Physics Division from October 1982 to January 1983. The original intent was to type the lecture notes. However, to finish the report in a reasonable time it was necessary to transcribe most of the equations by hand which led to certain notational difficulties. With a single exception in lecture no. 20, pp. 340-359, the notation has been made self-consistent by writing all script and other symbols by hand that are not easily reproduced by a word processor. Certain conventions should be noted. The superscript "ALT 216 symbol" is used to signal a footnote. However, the footnote is usually not to be found on the same page; in fact it may occur only after several intervening pages of text. Instructions are provided for interpreting the symbols representing the products of two vectors, as well as a note that important results are included in a box, with their relative importance being indicated by the number of asterisks associated with the box.

The battery is a key element in the acceptance of electric vehicles, and R and D efforts are being undertaken to improve battery performance and lifetime. In this electric-vehicle battery program, controlled laboratory tests were conducted to evaluate the effects of selected factors on the performance and life of the EV-2300 lead-acid battery manufactured by Johnson Controls, Inc. These factors included simulated driving profiles with different levels of peak power demands for vehicle acceleration, long rest times after charge or discharge, and different methods of recharging. The performance and cycle life of a 12-module full-scale battery pack and its support system were also evaluated. This report summarizes the work carried out on this program from January 1985 through April 1986. This work involved tests of the battery pack and support system, statistical analysis of capacity and power data from earlier tests of six-cell modules, and post-test analysis of selected modules and cells.

Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research. Fuel cycle work reported for this period includes testing of hydraulic performance and extraction efficiency of eight-stage centrifugal contactors, testing of a flowsheet for the Aralex process, evaluation of ruthenium and zirconium extraction in a miniature centrifugal contactor, study of zirconium aging in the organic phase and its effect on zirconium extraction and hydraulic testing of the 9-cm-ID contactor.

The second addition is a substantial revision of the original work. A new chapter on latent heat storage, an appendix on units and conversions, and an index have been added. The purpose for this manual is to provide information on the design and installation of thermal energy storage in solar heating systems. It is intended for contractors, installers, solar system designers, engineers, architects, and manufacturers who intend to enter the solar energy business. The reader should have general knowledge of how solar heating systems operate and knowledge of construction methods and building codes. Knowledge of solar analysis methods such as f-chart, SOLCOST, DOE-1, or TRNSYS would be helpful. The information contained in the manual includes sizing storage, choosing a location for the storage device, and insulation requirements. Both air-based and liquid-based systems are covered with topics on designing rock beds, tank types, pump and fan selection, installation, costs, and operation and maintenance. Topics relevant to latent heat storage include properties of phase-change materials, sizing the storage unit, insulating the storage unit, available systems, and cost. Topics relevant to heating domestic water include safety, single- and dual-tank systems, domestic water heating with air- and liquid-based space heating systems, and stand alone …

Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research.

A preliminary estimate has been made of the manufacturing cost for lithium/iron sulfide cells for stationary energy-storage and electric-vehicle applications. This preliminary cost analysis indicated that the manufacturing cost (in 1979 dollars) is $24 to 41/kW-h for stationary energy-storage cells and $31 to 55/kW-h for electric-vehicle cells. The materials cost was found to contribute between 52 and 65% of this manufacturing cost. The most expensive materials and components were lithium (metal and compounds), $4.61 to $14.26/kW-h; BN felt, $4.00 to 8.50/kW-h; feed-through components, $2.40/kW-h; positive current collectors, $1.48 to 2.20/kW-h; and aluminum, $1.43 to 1.66/kW-h. The projected lithium requirements were determined for use in lithium/iron sulfide batteries and conventional uses to the year 2006. The results showed that the lithium requirements were about 275,000 short tons by 2006, which is equivalent to about 51% of presently known US resources. Of this amount, about 33% would be used in battery production and 67% consumed in conventional uses. It is expected that the lithium used in battery production would be recycled.