Results of the Marysvale detailed geochemical survey are reported. Field and laboratory data are presented for 397 stream sediment samples and 160 radiometric readings. Statistical and areal distributions of uranium and possible uranium-related variables are displayed. A generalized geologic map of the area is provided, and pertinent geologic factors which may be of significance in evaluating the potential for uranium mineralization are briefly discussed. Stream sediments containing significant amounts of soluble uranium (greater than or equal to 16.93 ppM) occur in numerous areas, the most prevalent being in the western portion of the survey area, within and surrounding the Mount Belknap Caldera. Thorium, beryllium, cerium, manganese, molybdenum, niobium, potassium, yttrium, zinc, and zirconium occur in concentrations greater than or equal to 84th percentile in many sediment samples taken from within and surrounding the Mount Belknap Caldera. The uranium and related variables are associated with highly silicic intrusions and extrusions of the Mount Belknap Volcanics, as well as hydrothermal activity which has occurred in the Marysvale volcanic field.

Records of the Icelandic Population are being used to investigate the possible inheritance of disabilities and diseases as well as other characters and the effect of environment on man. The progress report of research covers the period 1977 to 1980. The investigation was begun in 1965 by the Genetical Committee of the University of Iceland and the materials used are demographic records from the year 1840 to present and various medical information. The records are being computerized and linked together to make them effective for use in hereditary studies.

Data collected as part of a hydrogeochemical and stream sediment reconnaissance of Grand Island NTMS quadrangle in Kansas and Nebraska including laboratory data on well water and stream sediments as well as field data.

Climatological data, both representative (typical) and extreme conditions, relevant to building energy use in Grandview, Missouri are presented. The energy-related characteristics of a particular building and its use are merged with ambient weather conditions. The graphs depict daily fluctuations in the major categories of building heating/cooling load for the experimental building (Roof Runner facility) at Butler Research Center. Data input include hourly weather and building occupancy schedules, the geometry and fixed thermal characteristics (component R-values, heat capacities, etc.) of the prototype structure, and variable conditions (status of moveable insulating shutters, HVAC operating modes, etc.). The prototype systems to be incorporated in the new Roof Runner building are shown. Both warehouse (no ceiling) and office (suspended ceiling) system types are included. The diagrams conceptually depict the heat flows in several representative operating modes, sampling the wide variety of operating conditions which will be evaluated during the testing phase of this project. Cost estimates for the designs selected for construction are provided. (MHR)

Records of the Icelandic population are being used to investigate the possible inheritance of disabilities and diseases as well as other characteristics and the effect of environment on man. The progress report of research covers the period from 1977 to 1980. The investigation was begun in 1965 by the Genetical Committee of the University of Iceland and the materials used are demographic records from the year 1840 to present and various medical information. The records are being computerized and linked together to make them effective for use in hereditary studies.

Progress is summarized concerning magnetic fusion energy materials, laser fusion energy, aluminium-air battery and vehicle, geothermal research, oil-shale research, nuclear waste management, office of basic energy sciences research, and materials research notes. (FS)

This report describes methodology for assessing the spatial patterns of radiological dose to man from wells drilled near nuclear waste repositories. Descriptions of the various categories of water wells and a model of a typical aquifer are presented. The equation governing the one-dimensional flow of waste in groundwater through porous media to a well is discussed. This is followed by development of a method for constructing lines of constant dose from a well located randomly in the plane of the aquifer. An area of hazard, in which the dose to man from a well exceeds a given statuatory or recommended limit, is then defined within this dose pattern. This technique is then used to compute dose and hazard profiles for wells adjacent to a repository located in either impermeable or permeable bedded salt. The repository and geologic parameters employed in this example are taken from a Lawrence Livermore Laboratory report for which this report serves as a supporting document. Scenarios with impermeable salt involve waste entering the repository through the shaft/tunnel fracture zone and exiting through a single additional flaw (borehole). Permeable-salt scenarios involve waste escaping from the repsitory through a borehole and via interstitial flow. Calculations are performed assuming …

This report contains a description of an analysis of generic nuclear waste repository in bedded salt. This analysis was performed by TASC for inclusion in a major Lawrence Livermore Laboratory report to NRC; this report therefore should be viewed as providing more complete and detailed information about this analysis than was possible to include in the LLL report. The analysis is performed with the NUTRAN computer codes which are described in the report. The model to be analyzed is defined, and the results of a series of possible waste migration scenarios are presented. Several of these scenarios are used as the basis for a sensitivity analysis, and an uncertainty analysis utilizing Monte Carlo techniques is also performed. A new method for defining the consequences to users of a well drilled near the repository is also described, and results are presented based on two of the waste migration scenarios.

Construction of an automated solar cell layup and interconnect system is now complete. This system incorporates a Unimate 2000 B industrial robot with an end effector consisting of a vacuum pick up and induction heating coil. The robot interfaces with a smart cell preparation station which correctly orients the cell, applies solder paste and forms and positions the correct lengths of interconnect lead. The system is controlled and monitored by a TRS-80 micro computer. The first operational tests of the fully integrated station have been run. These tests proved the soundness of the basic design concept but also pointed to areas in which modifications are necessary. These modifications are nearly complete and the improved parts are being integrated. Development of the controlling computer program is progressing to both reflect these changes and reduce operating time.

A two-step curve is expected in the potentiometric titration of Fe(II)-Sn(II) mixtures with Ce(IV) in H/sub 2/SO/sub 4/. Each end point should indicate the respective oxidation of Sn(II) and Fe(II). However, experimentally only one end point was found; it corresponded to the total oxidation of Sn(II) and Fe(II). When this oxidation-reduction reaction was carried out in the presence of Cl/sup -/, the theoretical behavior was observed. The present study was done to ascertain if monovalent anions other than Cl/sup -/ have a similar effect on this oxidation-reduction system. The monovalent species F/sup -/, Br/sup -/, and SCN/sup -/ were selected for this study, and the results indicate that each affects the rate of reaction relative to the ease of oxidation of the individual ions.

The recommended spring material for use in thermoelectric modules is either Inconel x or Elgiloy based on their excellent performance and availability. The stress level for generator applications is 75,000 psi. (FS)

Progress is reported in the following areas: AlGaAsSb/GaAsSb materials development, GaInP materials development via VPE, GaAlAs/GaAs cell development, and OM/CVD studies. Spectral response, V-I characteristics, and electron microprobe analysis results are presented. (WHK)

Results of a reconnaissance geochemical survey of the Corpus Christi Quadrangle, Texas, are reported. Field and laboratory data are presented for 119 groundwater samples and 57 stream sediment samples. Also included is a brief discussion on the geology and hydrology of the quadrangle. Groundwater data indicate that uranium concentrations above the 85th percentile occur primarily in a trend in western Nueces County. With one exception, waters in the trend are produced from the Evangeline aquifer and have high values for selenium and strontium. Owing to urbanization, low topographic relief, and the presence of Recent-to-Pleistocene surface material, stream sediment data were found to be less than optimum for the determination of the potential for uranium mineralization, and variation in uranium concentrations between units may simply reflect lithologic differences.

Early in this report period, the PDU was operated for a short time (one-half hour) before downstream constrictions prompted termination. The problem was traced to malfunction of the wetted-wall by-product condenser owing to the zinc chloride having a higher-than-anticipated viscosity near its melting point. Since then, a number of problems, minor in origin but major in effect, have hampered operation of the PDU. Steps are being taken to correct these deficiencies of design or mode of operation as they are revealed. Mathematical models were developed for testing against the data on the removal of zinc from silicon granules by vacuum heat treatment. With a suitable model confirmed, it will be possible to extrapolate the results to the larger particle size and different zinc content expected in the eventual product.

Results of the Edgemont detailed geochemical survey are reported. Field and laboratory data are presented for 109 groundwater and 419 stream sediment samples. Statistical and areal distributions of uranium and possible uranium-related variables are given. A generalized geologic map of the survey area is provided, and pertinent geologic factors which may be of significance in evaluating the potential for uranium mineralization are briefly discussed. Groundwaters containing greater than or equal to 7.35 ppB uranium are present in scattered clusters throughout the area sampled. Most of these groundwaters are from wells drilled where the Inyan Kara Group is exposed at the surface. The exceptions are a group of samples in the northwestern part of the area sampled and south of the Dewey Terrace. These groundwaters are also produced from the Inyan Kara Group where it is overlain by the Graneros Group and alluvium. The high uranium groundwaters along and to the south of the terrace are characterized by high molybdenum, uranium/specific conductance, and uranium/sulfate values. Many of the groundwaters sampled along the outcrop of the Inyan Kara Group are near uranium mines. Groundwaters have high amounts of uranium and molybdenum. Samples taken downdip are sulfide waters with low values of uranium …

The objective of this research is to investigate the technical feasibility of producing solar-cell-quality sheet silicon which could meet the DOE cost goals. The Honeywell approach is to coat one surface of carbonized ceramic substrates with a thin layer of large-grain polycrystalline silicon from the melt. Results and accomplishments which occurred during the quarter can be summarized as follows: (1) two major problems associated with SCIM-coating wide (10-cm) substrates were identified and solved; (2) the longitudinal temperature profile in SCIM-II has been improved to prevent substrate warping, buckling, and cracking; (3) the transverse temperature profile in SCIM II has been improved to produce more uniform coatings; (4) a strategy to eliminate effects of thermal stress has been developed; (5) the best SOC cell has a total-area conversion efficiency of 10.5% (AM1, AR), for a cell area of 5 cm/sup 2/; (6) a number of experiments are being investigated for improving cell efficiency; (7) for the slow-cooldown experiment, the average efficiency of 29 AR-coated cells was 9.9%, with a standard deviation of 0.3%; (8) encouraging results were obtained on SOC material that had been treated in a hydrogen plasma at Sandia; and (9) thermal modeling has proven to be beneficial in …

Site specific development plans are discussed for Caliente district heating and Winnemucca ethanol production. Outreach activities are listed. (MHR)

During FY 1980 work is being carried out on the following subtasks: evaluation of the thermal/hydraulic/mechanical consequences of enhanced fertile and fissile capture rates at interfaces; development of simpler ways to estimate interface capture rate enhancement; particularization of the breed/burn internal/external blanket management scheme; and participation in the Large Core Code Evaluation Working Group (LCCEWG) program.

The energy needs of Hamilton Air Force Base's Solar Village for electricity and heating and cooling of buildings are considered and alternative ways of meeting the Village's requirements for these forms of energy are evaluated. First, Solar Village's energy demand is calculated and compared to a base case representing calculations for typical energy usage for a development of similar size and density that is in conformance with current state and local ordinances. The potential of selected alternative technologies to meet the Solar Village projected demand for electrical power and natural gas is evaluated. Scenarios were developed to reduce demand, particularly in the building sector. Four alternative on-site energy technologies have been evaluated: wind, solar thermal electric, biomass conversion, photovoltaics. Each alternative is analyzed in detail. Of the four alternatives considered, the one with the greatest present potential is biomass conversion. Two technologies have been incorporated into the design. A 3-acre land fill is covered with a mantle of soil. A network of pipes carries off the methane gas which is a natural product of anaerobic decomposition of the materials in the land fill. The second technology involves the planting of rapidly-growing trees on denuded and unused portions of the site; …

An accountancy system based on the Dynamic Materials Accountability (DYMAC) System has been in operation at the Plutonium Processing Facility at the Los Alamos National Laboratory since January 1978. This system, now designated the Plutonium Facility/Los Alamos Safeguards System (PF/LASS), has enhanced nuclear material accountability and process control at the Los Alamos facility. The nondestructive assay instruments and the central computer system are operating accurately and reliably. As anticipated, several uses of the system, notably scrap control and quality control, have developed in addition to safeguards. The successes of this experiment strongly suggest that implementation of DYMAC-based systems should be attempted at other facilities.

The Multi-Megawatt Organic Rankine Engine (MORE) program is directed towards the development of a large, organic Rankine power plant for energy conservation from moderate temperature industrial heat streams. Organic Rankine power plants are ideally suited for use with heat sources in the temperature range below 1100/sup 0/F. Cement manufacture was selected as the prototype industry for the MORE system because of the range of parameters which can be tested in a cement application. This includes process exit temperatures of 650/sup 0/F to 1110/sup 0/F for suspension preheater and long dry kilns, severe dust loading, multi-megawatt power generation potential, and boiler exhaust gas acid dew point variations. The work performed during the Phase IA System Design contract period is described. The System Design task defines the complete MORE system and its installation to the level necessary to obtain detailed performance maps, equipment specifications, planning of supporting experiments, and credible construction and hardware cost estimates. The MORE power plant design is based upon installation in the Black Mountain Quarry Cement Plant near Victorville, California.

The potential engineering and economic feasibility of low-temperature geothermal energy applications on the campus of the University of New Mexico is studied in detail. This report includes three phases of work: data acquisition and evaluation, system synthesis, and system refinement and implementation. Detailed process designs are presented for a system using 190/sup 0/F geothermal water to substitute for the use of 135 x 10/sup 9/ Btu/y (141 TJ/y) of fossil fuels to provide space and domestic hot water heating for approximately 23% of the campus. Specific areas covered in the report include economic evaluation, environmental impact and program implementation plans.

The purpose of the task is to determine the market potential of the Brayton-cycle Subatmospheric System (SAS), especially as applied to the glass processing industry. Areas which impact the sales of the Brayton-cycle systems examined are: market size; opportunities for waste heat system installation (furnace rebuild and repair); pollution control on glass furnaces; equipment costs; equipment performance; and market growth potential. Supporting data were compiled for the glass industry inventory and are presented in Appendix A. Emission control techniques in the glass industry are discussed in Appendix B. (MCW)

The determination of the moisture content of /sup 238/Pu dioxide fuel for use in Milliwatt Generator heat sources was studied in an attempt to more clearly define the production fuel preloading procedures. The study indicated that water was not present or being adsorbed at various steps of the process (or during storage) that could lead to compatibility problems during pretreatment or long-term storage. The moisture content of the plutonium dioxide was analyzed by a commercial moisture analyzer. The moisture content at all steps of the process including storage averaged from 0.002% to 0.005%. The moisture content of the plutonium dioxide exposed to moist atmosphere for 7 days was 0.001%. These values indicated that no significant amount of moisture was adsorbed by the plutonium dioxide fuel charges. The only significant moisture content found was an average of 3.47%, after self-calcination. This was expected since no additional steps, other than self-heating of the fuel, are taken to remove the water.