The US Department of Energy initiated an investigation at Argonne National Laboratory in 1982 to experimentally determine the thermal stability limits and degradation rates of toluene as a function of maximum cycle temperature. Following the design and construction of a dynamic test loop capable of closely simulating the thermodynamic conditions of typical organic Rankine-cycle (ORC) power systems, four test runs, totaling about 3900 h of test time and covering a temperature range of 600-677(degree)F, were completed. Both liquid and noncondensable-vapor (gaseous) samples were drawn periodically and analyzed using capillary-column gas chromatography, gas chromatography/mass spectrometry, and mass spectrometry. A computer program that can predict degradation in an ORC engine was developed. Experimental results indicate that, if oxygen can be excluded from the system, toluene is a stable fluid up to the maximum test temperature; the charge of toluene could be used for several years before replacement became necessary. (Additional data provided by Sundstrand Corp. from tests sponsored by the National Aeronautics and Space Administration indicate that toluene may be used at temperatures up to 750(degree)F.) Degradation products are benign; the main liquid degradation products are bibenzyls, and the main gaseous degradation products are hydrogen and methane. A cold trap to remove …

The goal of this program is the development of a molten carbonate fuel cell (MCFC) anode which is more tolerant of sulfur contaminants in the fuel than the current state-of-the-art nickel-based anode structures. This program addresses two different but related aspects of the sulfur contamination problem. The primary aspect is concerned with the development of a sulfur tolerant electrocatalyst for the fuel oxidation reaction. A secondary issue is the development of a sulfur tolerant water-gas-shift reaction catalyst and an investigation of potential steam reforming catalysts which also have some sulfur tolerant capabilities. These two aspects are being addressed as two separate tasks.

This report documents recent progress on ground-water monitoring projects for four Hanford Site facilities: the 300 Area Process Trenches, the 183-H Solar Evaporation Basins, the 200 Area Low-Level Burial Grounds, and the Nonradioactive Dangerous Waste (NRDW) Landfill. The existing ground-water monitoring projects for the first two facilities named in the paragraph above are currently being expanded by adding new wells to the networks. During the reporting period, sampling of the existing wells continued on a monthly basis, and the analytical results for samples collected from September through November 1986 are included and discussed in this document. 8 refs., 41 figs., 7 tabs.

Three aerial radiological surveys were conducted during the period 16 June through 15 July 1986 over the towns of Pocatello, Soda Springs, and Fort Hall, Idaho and the surrounding areas. The surveys were performed for the United States Environmental Protection Agency (EPA) by the United States Department of Energy's (DOE) Remote Sensing Laboratory (RSL), utilizing the Aerial Measuring System (AMS). This work was completed in cooperation with a study by the EPA to conduct a dose assessment of human radiation exposure for industrial sources in Pocatello and Soda Springs, Idaho. The aerial surveys were performed to document the natural terrestrial radiological environment of the three localities and to map the spatial extent and degree of contamination due to phosphate milling operations. The results of these surveys will be used for planning ground-based measurements in addition to being incorporated into the dose assessment document. 4 refs., 14 figs., 6 tabs.

Estimated kokanee (Oncorhynchus nerka) abundance in Lake Pend Oreille was 4.3 million during September 1986. This estimate was similar to 1985 and indicates continued suppression of the kokanee population since initial decline in the late 1960s. Atypically high survival of wild fry resulted in similar fry recruitment in 1986 as 1985, whereas hatchery-reared fry contributed only 8% to total fry recruitment as a result of low post-release survival (3%). Fry released into the Clark Fork River from Cabinet Gorge Hatchery had very low survival during emigration to Lake Pend Oreille, resulting from poor flow conditions and potentially high predation. Fry survival during emigration was twice as high during nighttime flows of 16,000 cfs than 7,800 cfs. Emigration also was faster during higher flows. Several marks were tested to differentially mark fry release groups to help determine impacts of flow and other factors on fry survival. Survival of fry marked with tetracycline and fluorescent dye was high (>99%) during the 10-week study. In contrast, survival of fry marked with fluorescent grit marks ranged from 5 to 93%, depending on application pressure and distance from the fry. Retention was high (>96%) for tetracycline and grit marks during the study, whereas dye marks …

Online computer models of first order beam optics have been developed for the commissioning, control and operation of the entire SLC including Damping Rings, Linac, Positron Return Line and Collider Arcs. A generalized online environment utilizing these models provides the capability for interactive selection of a desired optics configuration and for the study of its properties. Automated procedures have been developed which calculate and load beamline component set-points and which can scale magnet strengths to achieve desired beam properties for any Linac energy profile. Graphic displays facilitate comparison of design, desired and actual optical characteristics of the beamlines. Measured beam properties, such as beam emittance and dispersion, can be incorporated interactively into the models and used for beamline matching and optimization of injection and extraction efficiencies and beam transmission. The online optics modeling facility also serves as the foundation for many model-driven applications such as autosteering, calculation of beam launch parameters, emittance measurement and dispersion correction.

The Eighth Annual DOE (Department of Energy) Low-Level Waste Management Forum was held in September 1986, in Denver, Colorado, to provide a forum for exchange of information on low-level radioactive waste (LLW) management activities, requirements, and plans. The one hundred ninety attendees included representatives from the DOE Nuclear Energy and Defense Low-Level Waste Management Programs, DOE Operations Offices and their contractors; representatives from the US Nuclear Regulatory Commission (NRC), US Environmental Protection Agency (EPA), US Geological Survey, and their contractors; representatives of states and regions responsible for development of new commercial low-level waste disposal facilities; representatives of utilities, private contractors, disposal facility operators, and other parties concerned with low-level waste management issues. Plenary sessions were held at the beginning and conclusion of the meeting, while eight concurrent topical sessions were held during the intervening two days. The meeting was organized by topical areas to allow for information exchange and discussion on current and future low-level radioactive waste management challenges. Session chairmen presented summaries of the discussions and conclusions resulting from their respective sessions. Selected papers in this volume have been processed for inclusion in the Energy Data Base.

The alignment of the Arcs for the Stanford Linear Collider at SLAC has posed problems in accelerator survey and alignment not encountered before. These problems come less from the tight tolerances of 0.1 mm, although reaching such a tight statistically defined accuracy in a controlled manner is difficult enough, but from the absence of a common reference plane for the Arcs. Traditional circular accelerators, including HERA and LEP, have been designed in one plane referenced to local gravity. For the SLC Arcs no such single plane exists. Methods and concepts developed to solve these and other problems, connected with the unique design of SLC, range from the first use of satellites for accelerator alignment, use of electronic laser theodolites for placement of components, computer control of the manual adjustment process, complete automation of the data flow incorporating the most advanced concepts of geodesy, strict separation of survey and alignment, to linear principal component analysis for the final statistical smoothing of the mechanical components.

Construction of the SLAC Linear Collider has posed some new problems in beam diagnostic device design. Typical beam sizes are small when compared with conventional storage rings, orbit tolerances are tighter and the pulsed nature of the machine means that signal to noise enhancement by averaging is not always possible. Thus the diagnostics must have high resolution, high absolute accuracy and must deliver data from a single pulse. In practice the required performance level depends on the function and dynamics of a given region in the collider. This paper reviews the major beam diagnostic systems and then discusses the global data acquisition schemes. Each system is described only in a very cursory fashion.

A shielding analysis for next generation of fusion devices (ETR/INTOR) was performed to study the dose equivalent outside the reactor building during operation including the contribution from neutrons and photons scattered back by collisions with air nuclei (skyshine component). Two different three-dimensional geometrical models for a tokamak fusion reactor based on INTOR design parameters were developed for this study. In the first geometrical model, the reactor geometry and the spatial distribution of the deuterium-tritium neutron source were simplified for a parametric survey. The second geometrical model employed an explicit representation of the toroidal geometry of the reactor chamber and the spatial distribution of the neutron source. The MCNP general Monte Carlo code for neutron and photon transport was used to perform all the calculations. The energy distribution of the neutron source was used explicitly in the calculations with ENDF/B-V data. The dose equivalent results were analyzed as a function of the concrete roof thickness of the reactor building and the location outside the reactor building.

All papers in this volume have been processed for inclusion in the Energy Data Base. (AT)

An X band klystron using a sheet beam and wiggler focusing was simulated using the 2 + 1/2 dimensional particle in cell code MASK. Simulation of the rf cavities was by means of the port approximation used in modelling of standard klystrons. The wigglers, which would need permanent magnets to achieve the required field strengths, were modelled using an idealized analytic expression with an exponential rise and a linear taper superimposed on a sinusoidal variation. Cavity locations and tunings were varied for maximum output power. Beam voltage and current were also varied to explore the effect on efficiency. Both an idealized laminar beam and a more realistic beam from a gun design code were studied. For a voltage of 200 kV and current of 20 amp per linear cm efficiencies of approximately 50% were calculated.

This plan defines the actions needed to achieve detection-level monitoring compliance at the Hanford Site 200 Areas Low-Level Burial Grounds (LLBG) in accordance with the Resource Conservation and Recovery Act (RCRA). Compliance will be achieved through characterization of the hydrogeology and monitoring of the ground water beneath the LLBG located in the Hanford Site 200 Areas. 13 refs., 20 figs.

Nine papers in this proceedings have been processed for inclusion in the Energy Data Base. (AT)

This paper gives a progress report on RF breakdown studies carried out at SLAC on an S-band standing-wave disk-loaded accelerator structure. The structure is the same as described at two earlier conferences but it has been equipped with eight new radial probes and one output port to observe the emission of light, which has not yet been used. The earlier breakdown limit of 144 MV/m equivalent traveling-wave accelerating gradient and 312 MV/m peak surface field has been reached again and possibly exceeded slightly even though the disk iris edges are severely pitted from earlier tests. Using the new probes it has become possible to monitor field emission as a function of azimuthal direction as well as to record the signals generated at the instant of breakdown. Results are given together with some information on the condition of the structure, chemical cleaning and RF processing. The paper ends with the presentation of some speculations and future plans.

This report contains the test results and assessments of seismic fragility tests performed on a 6-inch diameter piping system. The test was funded by the US Nuclear Regulatory Commission (NRC) and conducted by ETEC. The objective of the test was to investigate the ability of a representative nuclear piping system to withstand high level dynamic seismic and other loadings. Levels of loadings achieved during seismic testing were 20 to 30 times larger than normal elastic design evaluations to ASME Level D limits would permit. Based on failure data obtained during seismic and other dynamic testing, it was concluded that nuclear piping systems are inherently able to withstand much larger dynamic seismic loadings than permitted by current design practice criteria or predicted by the probabilistic risk assessment (PRA) methods and several proposed nonlinear methods of failure analysis.

Nominal predicted plasma conditions in a compact ignition tokamak are illustrated by transport simulations using experimentally calibrated plasma transport models. The range of uncertainty in these predictions is explored by using various models which have given almost equally good fits to experimental data. Using a transport model which best fits the data, thermonuclear ignition occurs in a Compact Ignition Tokamak design with major radius 1.32 m, plasma half-width 0.43 m, elongation 2.0, and toroidal field and plasma current ramped in six seconds from 1.7 to 10.4 T and 0.7 to 10 MA, respectively. Ignition is facilitated by 20 MW of heating deposited off the magnetic axis near the /sup 3/He minority cyclotron resonance layer. Under these conditions, sawtooth oscillations are small and have little impact on ignition. Tritium inventory is minimized by preconditioning most discharges with deuterium. Tritium is injected, in large frozen pellets, only after minority resonance preheating. Variations of the transport model, impurity influx, heating profile, and pellet ablation rates, have a large effect on ignition and on the maximum beta that can be achieved.

Hardware and software have been developed to permit computer control of the output of high power klystrons on a pulsed basis. Control of the klystron output is accomplished by varying the input drive via a pulsed rf attenuator. Careful power calibrations permit accurate calculation of the available energy, as seen by the beam, over the full range of the klystron output. The ability to control precisely the energy output allows for energy feed-forward as well as energy feedback applications. Motivation for this work has been the need to adjust the energy of beams launched into various regions of the SLC. Vernier klystrons play a crucial role in the energy delivered from the SLC injector, linac, and positron source. This paper discusses the hardware development, energy calculations, and software implementation. Operational results are presented.

The Energy Management Curriculum Starter Kit was designed to help engineering educators develop and teach energy management courses. Montana State University and Oklahoma State University courses are embodied in the model curriculum given. The curricula offered at many other universities throughout the United States are also presented. The kit was designed specifically to train engineering students to be good energy managers. Courses at both the undergraduate and postgraduate level are presented.

This report sets forth the Department's findings and recommendations for ensuring the safe management and disposal of low-level radioactive waste (LLW) with concentrations of radionuclides that exceed the limits established by the Nuclear Regulatory Commission for Class C LLW. Chapters are devoted to: Identification of Greater-Than Class-C Low-Level Waste; Regulatory Needs and Legislative Authorities; Proposed Actions to Ensure the Safe Management of Greater-Than-Class-C Low-Level Waste; System Considerations for Waste Disposal; Funding Options; Requirements for Implementation; and Schedule and Cost. Three Appendices are included: Public Law 99-240, Section 3(b); Greater-Than-Class-C Low-Level Waste Types and Quantities; and Descriptions of Systems Considerations for Waste Disposal. (LM)

A small, continuous liquid-fed mini-melter (LFMM) has been developed at Pacific Northwest Laboratory (PNL) to aid in waste glass feed slurry development. The LFMM offers several advantages over testing in large-scale melters. The LFMM requires little lead time in preparing for a test run, and the labor and material requirements are low. Real-time melting behavior of liquid feed slurries can be investigated, and feed rates can be estimated for larger-scale melters. The glass produced is representative of that produced by a larger-scale melter, as well as representative of the processing operation itself. Glass produced by the LFMM may subsequently be analyzed for metallic and other secondary phase formation. In contrast to larger-scale melters, the LFMM may be easily and inexpensively installed in a hot cell because of its relatively small size and simple configuration, enabling testing of radioactive feeds. A total of six LFMM experimental runs were performed. Feeds were obtained which corresponded to PNL melter runs performed in larger PNL developmental joule-heated research melters. These nonradioactive liquid-fed ceramic melters are known as the High-Bay Ceramic Melter (HBCM), the Experimental Ceramic Melter (ECM), and the Pilot-Scale Ceramic Melter (PSCM). Preliminary results obtained with the limited testing are promising. Feeds processed …

A survey is reported that addressed the question of shareable software for the High Energy Physics community. Statistics are compiled for the responses of 54 people attending a conference on the subject of shareable software to a questionnaire which addressed the usefulness of shareable software, preference of programming language, and source management tools. The results are found to reflect a continued need for shareable software in the High Energy Physics community and that this effort be performed in coordination. A strong mandate is also claimed for large facilities to support the community with software and that these facilities should act as distribution points. Considerable interest is expressed in languages other than FORTRAN, and the desire for standards or rules in programming is expressed. A need is identified for source management tools. (LEW)

The Mark III collaboration has performed a high statistics study of the reaction J/psi ..-->.. ..gamma..eta..pi../sup +/..pi../sup -/, with two different final states of the eta, eta ..-->.. ..gamma gamma.. and eta ..-->.. ..pi../sup 0/..pi../sup +/..pi../sup -/. Both modes have a broad structure from 1.2 to 1.9 GeV/c/sup 2/ and two structures, which decay via delta/sup + -/..pi../sup - +/, delta/sup + -/ ..-->.. eta..pi../sup + -/, are identified at 1.28 and 1.39 GeV/c/sup 2/. No signal is observed in the iota(1440) signal region.

We obtain spherically symmetric solutions for scalar fields with a non-minimal coupling xi absolute value of phi/sup 2/ R to gravity. We find, for fields of mass m, maximum masses and number of particles of order M/sub max/ approx. 0.73xi/sup 1/2/ M/sub Planck//sup 2//m, and N/sub max/ approx. 0.88xi/sup 1/2/ M/sub Planck//sup 2//m/sup 2/ respectively, for large positive xi. For large negative xi we find, M/sub max/ approx. 0.66 absolute value of xi/sup 1/2/ M/sub Planck//sup 2//m, and N/sub max/ approx. 0.72 absolute value of xi/sup 1/2/ M/sub Planck//sup 2//m/sup 2/.