Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes activities focuses on the development of electrolyte structures that have good electrolyte retention and mechanical properties as well as long term stability, and on developing methods of synthesis amenable to mass production.

Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during April 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.

This report describes the results of a study conducted by a "Pool Study Group" organized at ANL in mid-1975 to examine the present state of the air of design of pool-type LMFBRs. The study concentrated on examination of various design options used to date in the principle pool-type projects and design studies in this country and abroad, including the Phenix and Super-Phenix reactors (France), PFR and CFR (U.K.), RN-600 (U.S.S.R.) and EBR-II (U.S.A.). The objective of the report is to provide a step toward better understanding of the pool-type system and of the advantages and disadvantages of the various possible approaches to its design.

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 …

The Annex to the 7-GeV Advanced Photon Source Conceptual Design Report updates the Conceptual Design Report of 1987 (CDR-87) to include the results of further optimization and changes of the design during the past year. The design changes can be summarized as affecting three areas: the accelerator system, conventional facilities, and experimental systems. Most of the changes in the accelerator system result from inclusion of a positron accumulator ring (PAR), which was added at the suggestion of the 1987 DOE Review Committee, to speed up the filling rate of the storage ring. The addition of the PAR necessitates many minor changes in the linac system, the injector synchrotron, and the low-energy beam transport lines. 63 figs., 18 tabs.

Report describing the design and usage of the BORAX V nuclear reactor, its surrounding facility, systems, experimental programs, and possible hazards.

Report issued by the Argonne National Laboratory discussing the Experimental Boiling Water Reactor (EBWR) power plant. Designs of the final EBWR power plant are presented. This report includes tables, illustrations, and photographs.

The term modeling in the Workship title refers to the mathematical analysis of the consequences of many collision processes for characterizing the physical stage of radiation actions. It requires as input some knowledge of collision cross sections. Traditionally, work on cross sections and work on the modeling are conducted by separate groups of scientists. It was the purpose of the Workshop to bring these two groups together in a forum that would promote effective communication. Cross-section workers described the status of their work and told what data were available or trustworthy. Modeling workers told what kind of data were needed or were most important. Twenty-two items from the workshop were prepared separately for the data base.

Highlights of the Chemical Technology Division's activities during 1990, including electrochemical technology and advanced batteries and fuel cells, technology for coal-fired magnetohydrodynamics and fluidized-bed combustion, methods for recovery of energy from municipal waste, and techniques for treatment of hazardous organic waste, the reaction of nuclear waste glass and spent fuel under conditions expected for a high-level waste repository.

Report of Argonne Chemical Technology division activities, including high-performance batteries, aqueous batteries, advanced fuel cells, and coal utilization.

Highlights of the Chemical Technology (CMT) Division's activities during 1988 are presented. In this period, CMT conducted research and development in the following areas: (1) high-performance batteries (mainly lithium-alloy/metal sulfide, sodium/metal chloride, and sodium/sulfur); (2) aqueous batteries (lead-acid, nickel/iron, etc.); (3) advanced fuel cells with molten carbonate or solid oxide electrolytes; (4) coal utilization, including the heat and seed recovery technology for coal-fired magnetohydrodynamics plants and the technology for fluidized bed combustion; (5) methods for recovery of energy from municipal waste and techniques for treatment of hazardous chemical waste; (6) nuclear technology related to a process for separating and recovering. transuranic elements from nuclear waste and for producing 99Mo from low-enriched uranium targets, the recovery processes for discharged fuel and the uranium blanket in a sodium-cooled fast reactor, and waste management; and (7) physical chemistry of selected materials in environments simulating those of fission and fusion energy systems.

Computer graphic representation of the antigen-binding sites of two Bence-Jones proteins (antibody light chain diners), Loc (left) and Mcg (right). The spheres represent individual amino acids. Each binding site is composed of two variable domains and each domain consists of framework segments and the hyper-variable segments which confer the specificity to the antibody molecule.

Annual report of the Argonne National Laboratory Radiological and Environmental Research Division regarding activities related to the Center for Human Radiobiology. This report discusses an inquiry into the mechanisms and dosimetry for induction of malignancies by radium, and studies of individuals exposed to radium and thorium, as well as to other radionuclides,.

TREAT F-series tests are being conducted to provide data on fuel motion in an LMFBR during a hypothetical loss-of-flow accident. Fuel and fuel-boundary conditions in an LMFBR subassembly following sodium voiding and dryout under loss-of-flow conditions are simulated in each F-series test. Simulation is achieved with a single fuel element surrounded by an annular nuclear-heated wall in a dry (no sodium) test capsule. The area inside the heated wall was selected to represent the area inside the perimeter of an LMFBR coolant channel. Test F1 was conducted with an irradiated fuel element to investigate the effect of fission gas on fuel motion at design power levels following cladding melting and drainage. The principal conclusion from Test F1 is that fission products retarded, but did not prevent, eventual fuel collapse. The collapse was retarded by a fuel/fission-product froth that prevented fuel collapse until the fission products separated from the partially molten fuel. The fuel motion observed in F1 represents a particular type of fuel (burnup of 2.35 at.%, power rating of 394 W/cm) transient heated at design power rating.

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.

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.

Report on technical progress in the various research and assessment activities of Argonne National Laboratory.

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).

Report issued by the Argonne National Laboratory discussing the thermodynamics and electronic distribution of high temperatures. As stated in the introduction, "in the present paper, a model for computing is described which takes into account in detail the interactions between bound electrons and the average interaction of the bound electrons with the free ones" (p. 4). This report includes tables, and illustrations.

An outline is presented for an experimental program to develop and evaluate nondestructive assay techniques applicable to holdup measurement in plutonium-containing fuel fabrication facilities. The current state-of-the-art in holdup measurements is reviewed. Various aspects of the fuel fabrication process and the fabrication facility are considered for their potential impact on holdup measurements. The measurement techniques considered are those using gamma-ray counting, neutron counting, and temperature measurement. The advantages and disadvantages of each technique are discussed. Potential difficulties in applying the techniques to holdup measurement are identified. Experiments are proposed to determine the effects of such problems as variation in sample thickness, in sample distribution, and in background radiation. These experiments are also directed toward identification of techniques most appropriate to various applications. Also proposed are experiments to quantify the uncertainties expected for each measurement.

A nondestructive autoradiographic method is described which can provide a verification that rods in the interior of unirradiated LWR fuel assemblies contain low-enriched uranium. Sufficient absorber must be used to reduce contributions to image density by beta radiation from uranium-238 daughters. When appropriate absorbers are used, the density of the image of a uranium-containing fuel rod is proportional to the uranium-235 enrichment in that rod. Exposure times as short as 1.5 hours can be achieved by using fast film and intensifying screens. Methods are discussed for reducing contributions to the image density of any single rod from radiation produced by all other rods in the assembly. The technique is useful for detecting missing rods, dummy rods, and rods containing depleted uranium. These defects can be detected by visual inspection of the autoradiographs. In its present state of development, the technique is not sensitive enough to reliably detect the difference between the various uranium-235 enrichments encountered in current BWR fuel assemblies. Results are presented for field tests of the technique at BWR and PWR facilities.

This report discusses experiments with various ways to conduct a magnetically assisted chemical separation (MACS) process, designed to separate transuranic (TRU) elements out of high-level waste (HLW) or TRU waste.

This report summarizes and documents the efforts of Argonne National Laboratory (ANL) in developing a secure tag communication user interface program comprising a tag monitor and a communication tool. This program can perform the same functions as the software that was developed at the Lawrence Livermore National Laboratory (LLNL), but it is enhanced with a user-friendly screen. It represents the first step in updating the TRANSCOM Tracking System (TRANSCOM) by incorporating a tag communication screen menu into the main menu of the TRANSCOM user program. A working version of TRANSCOM, enhanced with ANL secure-tag graphics, will strongly support the Department of Energy Warhead Dismantlement/Special Nuclear Materials Control initiatives. It will allow commercial satellite tracking of the movements and operational activities of treaty-limited items and transportation vehicles throughout Europe and the former USSR, as well as the continental US.

The thermal cycling growth and the accompanying metallographic changes were studied in 300 [degree] C rolled uranium rods up to 3000 cycles. The growth rate was found to decrease at the higher cycling levels. Project-grade material developed substantial porosity during cycling; high purity material showed no evidence of porosity.