The environmental levels of radioactivity and other pollutants found in the vicinity of BNL during 1983 are summarized. The amounts of radioactivity and other pollutants released in airborne and liquid effluents from Laboratory facilities to the environment are also indicated. The environmental data includes external radiation levels; radioactivity of air particulates; tritium concentrations; the amounts and concentrations of radioactivity in and the water quality of the stream into which liquid effluents are released; the concentrations of radioactivity in biota from the stream; the concentrations of radioactivity in and the water quality of ground waters underlying the Laboratory; and concentrations of radioactivity in milk samples obtained in the vicinity of the Laboratory. The amounts of radioactivity released in airborne and liquid effluents from laboratory facilities to the environment were within allowable standards as stipulated in DOE Order 5480.1. Other pollutants, such as metals, organic compounds, etc., in the effluents released from the Laboratory were well below federal, state and local standards as applied to site specific conditions. 34 references, 9 figures, 17 tables.

Acoustic emission (AE) monitoring of selected pressure boundary areas at TVA's Watts Bar, Unit 1 Nuclear Power Plant during hot functional preservice testing is described in this report. The report deals with background, methodology, and results. The work discussed here is a major milestone in a program supported by NRC to develop and demonstrate application of AE monitoring for continuous surveillance of reactor pressure boundaries to detect and evaluate growing flaws. The subject work demonstrated that anticipated problem areas can be overcome. Work is continuing toward AE monitoring during reactor operation.

Newsletter issued by the Advisory Council for Technical-Vocational Education in Texas discussing news, events, and other relevant information related to technical and vocational education for adults in Texas.

The present backlog of irradiated reactor fuel leads to projections that no fuel out of the reactor less than 10 years need be reprocessed prior to the year 2000. The only radioiodine present in such aged fuel is /sup 129/I (half-life 1.6 x 10/sup 7/ y). The /sup 131/I initially present in the fuel decays to insignificance in the first few hundred days post-reactor. The /sup 129/I content of irradiated fuel is about 1 Ci per gigawatt-year of electricity generated (Ci/GW(e)-y). The US EPA has specified, in 40 CFR 190, a release limit for /sup 129/I of 5 mCi/GW(e)-y. Thus a retention factor (RF) of 200 for /sup 129/I at the fuel reprocessing plant (FRP) is required. Experience indicates that RF values obtained under actual FRP operating conditions can average as little as 10% of experimentally determined RF values. Therefore processes theoretically capable of achieving RF values of up to 10/sup 4/ have been investigated. The US EPA has also specified in 40 CFR 90 a thyroid dose limit of 75 mrem/y for a member of the general public. This dose limit could be readily met at a typical FRP site with an RF value of about 10 or less. …

Sensitivity analysis of practical problems can be performed systematically and very efficiently by using adjoint functions. In areas of interest to nuclear reactors, this efficiency has been amply demonstrated on several widely used codes for neutronics and/or thermal hydraulic calculations. Applications of the adjoint method of sensitivity analysis to models involving phase transitions, where non-differentiability occurs, do not seem to have been reported to date. The purpose of this paper is to report results from a successful adjoint sensitivity analysis of a space- and time-dependent system where phase transition occurs due to boiling. The specific model chosen for this analysis is a simplified but representative model of a BWR pump-trip-type accident. This model is of particular importance to BWR safety, since pump failure is one of the most limiting hypothetical accidents in BWR's. This model simulates an exponential flow decay of initially subcooled FREON-114 flowing through a heated channel and undergoing boiling transition.

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

This first quarterly report documents technical progress during the period 31 December 1983 through 30 March 1984. The technical effort is 17 months in duration and is divided into two major technical tasks: Task VII, Hardware Fabrication and PDU Modifications, and Task VIII, Performance Testing. The design of test hardware and process development unit modifications had been previously completed as part of Task VI of the current contract. Task VII involves the fabrication of test hardware and modification of an existing 1-ton/h hydroliquefaction PDU at Rockwell's facilities for use as a hydrogasifier test facility. During this report period, fabrication of the test hardware and modifications to the PDU were initiated. Test hardware fabrication is now approximately 80% complete and should be completed by the end of May 1984. PDU modifications are progressing well and should be completed by the end of June 1984. The completed test hardware fabrication and PDU modifications will allow the conduct of short duration (1 to 2 h) hydrogasification tests along with preburner assembly performance evaluation tests in order to fulfill the test program objectives. Separate supplies of hydrogen, oxygen, methane, carbon monoxide, and water (for steam generation) are provided for this purpose. The modified facility …

The English translations of four classic research papers in Alpine meteorology, originally published in German and French in the 1930s and 1940s are presented in this report. The papers include: A. Wagner's 1938 paper entitled Theory and Observation of Periodic Mountain Winds; E. Ekhart's 1944 paper entitled Contributions to Alpine Meteorology; E. Ekhart's 1948 paper entitled On the Thermal Structure of the Mountain Atmosphere; and F. Defant's 1949 paper entitled A Theory of Slope Winds, Along with Remarks on the Theory of Mountain Winds and Valley Winds. A short introduction to these translations summarizes four recent Alpine meteorology field experients, emphasizing ongoing research that extends the research of Wagner, Ekhart, and Defant. The four experiments include the Innsbruck Slope Wind Experiment of 1978, the MESOKLIP Experiment of 1979, the DISKUS Experiment of 1980, and the ALPEX/MERKUR Experiment of 1982.

Detailed fracture logging and analysis of the UG-2 core from the Climax Stock is reported. This borehole is about 183 m long (600 ft) and slants downward below the Spent Fuel Test workings, thus representing the only sampling of the quartz monzonite at depth. An effective means of orienting the core sections relative to a certain joint set of known orientation is demonstrated, and a computational procedure for accomplyishing this in non-vertical boreholes is presented. Although this core orienting scheme is approximate, modal joint set orientations could be estimated. A distinctive low-angle joint set which pervades the existing workings is the most frequently encountered set at depth, and its spacing distribution is shown to be negative exponential. The next common joint set in the core strikes northeasterly and dips steeply to the southeast. Another set strikes northwesterly and is nearly vertical. These groupings generally agree with results of previous surveys in the area, which suggests the rock mass is homogeneous in terms of its joint pattern. 13 references, 25 figures, 2 tables.

The optical and structural load deformation response behavior of a uniform pressure-loaded stretched-membrane reflective module subject to nonaxisymmetric support constraints is studied in this report. To aid in the understanding of this behavior, an idealized analytical model is developed and implemented and predictions are compared with predictions based on the detailed structural analysis code NASTRAN. Single structural membrane reflector modules are studied in this analysis. In particular, the interaction of the frame-membrane combination and variations in membrane pressure loading and tension are studied in detail. Variations in the resulting lateral shear load on the frame, frame lateral support, and frame twist as a function of distance between the supports are described as are the resulting optical effects. Results indicate the need to consider the coupled deformation problem as the lateral frame deformations are amplified by increasing the membrane tension. The importance of accurately considering the effects of different membrane attachment approaches is also demonstrated.

This report talks about Aperture Dependence Of RHIC Cells On Multipole Fields In The Dedicated RHIC Dipoles.

The PATRICIA and RACETRACK particle tracking programs have been compared by tracking on a simple lattice. The dynamic aperture was found to decrease as the number of passes through the lattice per run increased from 20 to approx. 300, and it remained constant for longer runs. The dynamic apertures found by the two programs are consistent. The dependence of the dynamic aperture on horizontal tune near a decapole resonance was investigated. RACETRACK and PATRICIA showed decreases in the aperture on opposite sides of the resonance. A second set of studies was made with PATRICIA in which the dynamic apertures of lattices consisting of cells of the types used for the Reference Designs Study were determined when random multipole errors of the dipoles were included. The dependence of aperture on the number of cells in the lattice was determined. Finally, a comparison of magnet types suggested for the SSC was made by determining the aperture of lattices containing these magnets.

This progress report describes the activities of the Los Alamos Nuclear Data Group for April 1, 1983 through September 30, 1983. Topics covered include theory and evaluation of nuclear cross sections; nuclear cross-section processing and testing; neutron activation; fission products, and actinides; and core neutronics code development in support of LMFBR carbide core assessment. (GHT)

The functions to be performed by the ATA diagnostic data handling system are discussed. The capabilities of the present data acquisition system (System 0) are presented. The goals for the next generation acquisition system (System 1), currently under design, are discussed. Facilities on the Octopus system for data handling are reviewed. Finally, we discuss what has been learned about diagnostics and computer based data handling during the past year.

The first gas propagation experiment on ATA is planned to be conducted in a 1-foot diameter tank of up to 10 m length. The primary objectives are to measure beam parameters at injection to determine whether the desired beam conditioning is achieved, and to observe how such conditioned beams propagate in air and neon.

The philosophy of these tests is to measure the motion of a low current, small diameter electron beam in the accelerator before running high current. By using low current, we can study particle motion in the applied fields without any extra complications associated with the self-forces of high currents. With the steering magnets off, we have measured the transverse drift of the probe beam. Also, we have used the probe beam to optimize the current in the steering magnets to compensate for the drift. There have been concurrent efforts to locate the source of the error field which is presumed to cause the drift. So far, the source has not been established but the search is continuing.

The beam-cavity coupling impedance is formulated in terms of the normal modes of the cavity. While the analysis is carried out only for the longitudinal beam-cavity coupling impedance, it should be easily adapted to the transverse impedance. The hope is that such a formulation may illuminate the behavior of the coupling impedance in various frequency limits.

Results pertaining to the recently modified beam-injection arrangement in the central cell of TMX-U are presented here. These modifications followed our observation that beam atoms injected perpendicular to the magnetic axis between the first two magnet-coil gaps give rise to trapped ions with midplane pitch angles lying in the intervals 68/sup 0/ < theta < 78/sup 0/ and 59/sup 0/ < theta < 65/sup 0/. These pitch-angle intervals are similar in value to the earlier arrangement of beams injected at the midplane at pitch angles of 58 and 70/sup 0/. Normal injection at an off-midplane position has two advantages when compared with off-normal injection at the midplane. First, the unattenuated beam can be dumped in the first-injector region rather than in the plasma region. Second, the beams can be oriented with their long dimension horizontal rather than vertical. The first point al

The term complex mixture has been recently applied to energy-related process streams, products and wastes that typically contain hundreds or thousands of individual organic compounds, like petroleum or synthetic fuel oils; but it is more generally applicable. A six-year program of ecological research has focused on four areas important to understanding the environmental behavior of complex mixtures: physicochemical variables, individual organism responses, ecosystems-level determinations, and metabolism. Of these areas, physicochemical variables and organism responses were intensively studied; system-level determinations and metabolism represent more recent directions. Chemical characterization was integrated throughout all areas of the program, and state-of-the-art methods were applied. 155 references, 35 figures, 4 tables.

LIFE-4C is a steady-state/transient analysis code developed for performance evaluation of carbide ((U,Pu)C and UC) fuel elements in advanced LMFBRs. This paper summarizes selected results obtained during a crucial step in the development of LIFE-4C - benchmark and physics testing.

Calculation of the neutron multiplication factor at delayed criticality may be necessary for benchmarking calculations but it may not be sufficient. The use of subcritical experiments to benchmark criticality safety calculations could result in substantial savings in fuel material costs for experiments. In some cases subcritical configurations could be used to benchmark calculations where sufficient fuel to achieve delayed criticality is not available. By performing a variety of measurements with subcritical configurations, much detailed information can be obtained which can be compared directly with calculations. This paper discusses several measurements that can be performed with subcritical assemblies and presents examples that include comparisons between calculation and experiment where possible. Where not, examples from critical experiments have been used but the measurement methods could also be used for subcritical experiments.

The Berkeley Mini-Collider, a heavy-ion collider being planned to provide uranium-uranium collisions at T/sub cm/ less than or equal to 4 GeV/nucleon, is described. The central physics to be studied at these energies and our early ideas for a collider detector are presented.

Biooxidation is an important part of the overall wastewater treatment system for the proposed SRC-I Demonstration Plant in Newman, Kentucky. After the completion of a Baseline Design for the plant in April 1982, various refinements were evaluated. One of these was the inclusion of a process for phenol recovery from four sour-water streams. As part of this evaluation, an extensive laboratory treatability study was conducted on wastewaters both with and without this phenol recovery step. The purpose of the study was to compare the results of different treatment schemes on different wastewaters and did not include the development of the kinetic coefficients that govern the biooxidation process. Additional treatability testing documented herein, has been performed to establish the kinetic coefficients for biooxidation of the SRC-I wastewaters. This will provide a rational basis for any subsequent changes in design. The wastewater feed used in this study was process recycle water from the Fort Lewis, Washington, pilot plant. Prior to biooxidation, it was pretreated by solvent extraction for removal of phenolics and by steam stripping for removal of ammonia and hydrogen sulfide. Two, 2-stage bench scale bioreactors were operated for approximately eight months, during which time they were stabilized at various steady-state …

This paper describes numerical techniques for calculating the capacitance of an arbitrary two conductor structure. For two dimensional structures the capacitance per unit length can be easily related to the characteristic impedance of a transmission line with the same cross section. Note that this is true for lines operated below their cut off frequency, i.e., TEM mode only. Thus, one can compute the impedance of an arbitrarily shaped line. The method using the ANSYS finite element program is being used to design the high voltage transmission line for the Yale streamer chamber. This line has a transition piece between two different cross sections. It is being modeled by taking several slices throughout the transition region.