Extensive modifications were made to the multi-source deposition apparatus. These include the installation of a larger vacuum chamber on the existing system. The new chamber provides improved inter-source shielding, an improved substrate mounting and heating system, and a vacuum interlock for introducing substrates. CdS resistivity control by both In doping and off-stoichiometric deposition has been investigated. Indium doping has been achieved both by diffusion from a pre-deposited In layer and by using In doped sputtering targets. Resistivities in the range 0.1 to 5 ..cap omega..-cm have been obtained for target doping levels of from 0.1 to 1 at. percent of In. These resistivities were found to be critically dependent on the H/sub 2/S injection rate, apparently because of compensation by Cd vacancies. Off-stoichiometry CdS coatings with solar-illuminated resistivities of about 10/sup 2/ ..cap omega..-cm have been deposited, using a cyclic reactive sputtering process were the H/sub 2/S injection is periodically switched on and off. The Cu/sub x/S deposition process was found to be sensitive to the period of cathode operation prior to coating deposition, probably because of the conditioning of cathode and shield surfaces. All-sputter-deposited Cd(Zn)S/Cu/sub 2/S cells, with Cd(Zn)S layers deposited using a Cd-0.10 Zn target doped with 2 …

The advantages and disadvantages of four new high-resolution difference schemes, namely the von Neumann-Richtmyer, Godunovs, MUSCL and Glimms, for mathematically representing physical conditions in compressible gas flows are compared. (LCL)

The University of Tennessee Space Institute (UTSI) reports on significant activity, task status, planned research, testing, development, and conclusions for the Magnetohydrodynamics (MHD) Coal-Fired Flow Facility (CFFF) and the Research and Development Laboratory. Although slowed by incessant rain during several days, work on the CFFF Bid Packages progressed to nearly 100 percent completion, excluding later punchlist items. On the quench system, the cyclone separator was delivered to UTSI, and under Downstream Components, the secondary combustor was received and the radiant slagging furnace was emplaced at the CFFF. Water quality analysis of Woods Reservoir provided the expected favorable results, quite similar to last year's. Generator experiments describing local current distribution are reported along with behavior under conditions of imposed leakage. Also, during the Quarter, the shelter for the cold flow modeling facility was constructed and circuits installation begun. A jet turbine combustor was tested for use as a vitiation burner. Samples taken from the exhaust duct, besides other applications, show that the refractories used are performing well in alleviating heat loss while exhibiting acceptable degredation. A new resistive power take-off network was designed and implemented.

Fusion research has matured during the last decade and significant insight into the future program needs has emerged. While some will properly note that the crystal ball is cloudy, it is equally important to note that the shape and outline of our course is discernable. In this short summary paper, I will draw upon the National Mirror Program Plan for mirror projects and on available design studies of these projects to put the specific needs of the mirror program in perspective.

Rock samples from the Salton Sea Geothermal Field (sandstone, tuff, granite) and from accretionary prism sediments along the convergent margins in southeast Alaska and southwest Japan have been dated by the /sup 40/Ar/sup 39/Ar method. Paleotemperatures have been calculated. (ACR

The use of carbonaceous adsorbents is limited by irreversible adsorption of some compounds so the use of supercritical pentane as an extracting solvent was examined. Carbon black appeared to be broken down slowly, but continuously, by the penane. To see if other types of carbon behaved similarly, high purity graphite, technical grade graphites, active carbons, and charcoals were examined. The extracts were characterized by uv spectroscopy, packed column chromatography using flame ionization and flame photometric detectors, and capillary GC/MS. The extracts were characteristic for each class of carbonaceous material. The high purity graphite yielded large, polycyclic aromatic compounds; the technical grade graphites yielded alkanes and alkyl-substituted benzenes and naphthalenes; the active carbons yielded alkanes, dienes, and small amounts of alkyl-substituted benzenes; and the charcoals yielded almost entirely alkanes in small amounts.

This quarterly report includes summaries of the following tasks: (1) OTEC pilot plant conceptual design review; (2) OTEC methanol; (3) management decision requirements for OTEC construction; (4) hybrid geothermal - OTEC (GEOTEC) power plant performance estimates; and (5) supervision of testing of pneumatic wave energy conversion system.

The experimental solar collector systems at Middlebury College have been modified to permit short time resolution studies of solar collector loop performance. A variety of experiments have been performed to measure the following system properties: (a) collector efficiency, (b) collector response to step changes in insolation, (c) collector response to the introduction of cold inlet water, and (d) pump cycling as a function of control sensor location and set points. Data from these experiments have been supplied to the solar group at Drexel for validation of their analytical collector loop model.

This Resource Conservation and Recovery Act (RCRA) Facility Investigation Program Plan has been developed to provide a framework for the completion of RCRA Facility Investigations (RFI) at identified units on the Savannah Rive Site (SRS) facility. As such, the RFI Program Plan provides: technical guidance for all work to be performed, managerial control, a practical, scientific approach. The purpose of this Overview is to demonstrate how the basic RFI Program Plan elements (technical, management, and approach) are interwoven to provide a practical and workable plan. The goal of the RFI Program Plan is to provide a systematic, uniform approach for performance and reporting. In addition, the RFI Program Plan has been developed to be specific to the SRS facility and to adhere to the Environmental Protection Agency (EPA) RFI guidance received as part of the SRS. The US EPA publication Characterization of Hazardous Waste Sites'' has been liberally adapted for use in this RFI Program Plan.

Progress and activities are reported on component development, pilot plant development, and instrumentation and statistical systems. Specific items studied include processing of pond sludge, transport of radioactive materials and wastes, corrosion, decontamination and cleaning, fluidized-bed incineration, Pu contamination of soils, chemical analysis, radiometric analysis, security. (DLC)

Data were reduced from the voltage-time relations stored in files D7H001 to D7H090 on HP1000. The I-B calibration curve is included. The data base is shown and can be used by the 9845B. The data include the quench location, Q/sub 2/ layer 1 top, Q/sub 3/ layer 1 bottom and the quench current and its normalized value with respect to short sample, I/sub c/ = 4920A at 4.4 K, I/sub c/ = 6710 A at 1.8 K. The resistance (..cap omega../cm) was calculated using the propagation time according to the voltage change across the measured sections. The conductor potential length are L/sub 5/ /sub 9/ = 48.6 cm, L/sub 6/ /sub 10/ = 17.9 cm, L/sub 7/ /sub 11/ = 40.6 cm. The turn to turn velocity V/sub t/ was calculated dividing the nominal turn to turn distance (58 mil) by the propagation time (Trans. Time). The quench time T/sub q/ was measured from the time the resistive rise starts until the energy extraction system fires.

Double mode pulsation is a very pervasive phenomenon in stars all over the Hertzsprung-Russell diagram. In order of increasing radius, examples are: ZZ Ceti stars, the sun, the delta Scuti stars, RR Lyrae variables, the ..beta.. Cephei variables and those related to them, Cepheids, and maybe even the Mira stars. These many modes have been interpreted as both radial and nonradial modes, but in many cases the actual mode has not been clearly identified. Yellow giants seem to be the most simple pulsators with a large majority of the RR Lyrae variables and Cepheids showing only one pulsation period. We limit this review to those very few cases for classical Cepheids and RR Lyrae variables which display two modes. For these we know many facts about these stars, but the actual cause of the pulsation in two modes simultaneously remains unknown.

A chemically stabilized coal-oil mixture (COM) was made and used as an auxiliary fuel in a blast furnace for 44 days. Approximately 485,000 gallons of COM were produced at an on-site COM plant. Composition was 47.9% coal, 47.6% No. 6 oil, 4.0% water, and 0.5% emulsifier. Average injection rates were 3.8 to 13.0 gpm during different periods of the trial. Coal handling equipment, mixing and processing equipment, pumps, piping, fuel lances, and instrumentation are discussed. The blast furnace performance during the trial is compared to a Base Period of injecting No. 6 oil. Blast furnace performance was satisfactory, with one pound of COM replacing one pound of coke or 0.8 pound of No. 6 oil. The production of COM and its usage in a blast furnace is economical and feasible.

Disposal of high-level radioactive wastes is a major environmental problem influencing further development of nuclear energy in this country. Salt domes in the Gulf Coast Basin are being investigated as repository sites. A major concern is geologic and hydrologic stability of candidate domes and potential transport of radionuclides by groundwater to the biosphere prior to their degradation to harmless levels of activity. This report conceptualizes a regional geohydrologic model for transport of radionuclides from a salt dome repository. The model considers transport pathways and the physical and chemical changes that would occur through time prior to the radionuclides reaching the biosphere. Necessary, but unknown inputs to the regional model involve entry and movement of fluids through the repository dome and across the dome-country rock interface and the effect on the dome and surrounding strata of heat generated by the radioactive wastes.

One of the primary objectives of the MFTF-B upgrades is to demonstrate the technology of tritium breeding in a reactor-like configuration. This requires use and processing of tritium, involving an inventory of several hundred grams at the plant. This paper reviews the results of a preliminary assessment of the radiation hazard associated with the handling of tritium. The radiation dose consequences due to tritium release from normal operation and due to postulated accidents on plant personnel and the public were assessed. Maximum credible (probability < 10/sup -3/, but > 10/sup -7//yr) accidental releases were estimated to be 10 gm in the reactor building and 100 gm in the tritium-processing building. Higher probability (> 10/sup -3//yr) accidents or component failures would result in much smaller releases. In the reactor building, the most severe accident would result from the rupture of a plasma exhaust duct from the end cell or the tritium feed pipe to the neutral beam injector, accompanied by a fire. In the tritium processing building, the most severe accident would be the rupture of the Isotope Separation System (ISS) distillation columns and vacuum jackets accompanied by a fire.

Critiques are presented of the Conservation and Solar Office strategy papers on the building, public utility, transportation, and industrial sectors. (MCW)

The most important potential environmental problems uniquely associated with indirect liquefaction appear to be related to the protection of occupational personnel from the toxic and carcinogenic properties of process and waste stream constituents, the potential public health risks from process products, by-products and emissions and the management of potentially hazardous solid wastes. The seriousness of these potential problems is related partially to the severity of potential effects (i.e., human mortality and morbidity), but even more to the uncertainty regarding: (1) the probable chemical characteristics and quantities of process and waste streams; and (2) the effectiveness and efficiencies of control technologies not yet tested on a commercial scale. Based upon current information, it is highly improbable that these potential problems will actually be manifested or pose serious constraints to the development of indirect liquefaction technologies, although their potential severity warrants continued research and evaluation. The siting of indirect liquefaction facilities may be significantly affected by existing federal, state and local regulatory requirements. The possibility of future changes in environmental regulations also represents an area of uncertainty that may develop into constraints for the deployment of indirect liquefaction processes. Out of 20 environmental issues identified as likely candidates for future regulatory action, …

The activities of the Geothermal Office during the quarter are discussed, including: important geothermal events, geothermal waste disposal, a grant award by the California Energy Commission, the geothermal development meeting, and the current status of geothermal development in Imperial County. Activities of the Geothermal Planner are addressed, including permits, processing of EIR's, and other planning activities. Progress on the direct heat study is reported.

The NOVA laser consists of ten beams, capable of concentrating 100 to 150 kJ of energy (in 3 ns) and 100 to 150 TW of power (in 100 ps) on experimental targets by 1985. NOVA will also be capable of frequency converting the fundamental laser wavelength (1.05 ..mu..m) to its second (0.525 ..mu..m) or third (0.35 ..mu..m) harmonic. This additional capability (80 to 120 kJ at 0.525 ..mu..m, 40 to 70 kJ at 0.35 ..mu..m) was approved by the US Department of Energy (DOE) in April 1982. These shorter wavelengths are much more favorable for ICF target physics. Current construction status of the NOVA facility, intended for completion in the autumn of 1984, will be presented.

The CORCON-MOD1 core material-concrete interaction code, developed at the Sandia Laboratories for LWR safety analysis, was adapted for analyzing a postulated LMFBR core melt accident.

The new radiation dose estimates for Hiroshima and Nagasaki are here combined with epidemiologic data from the A-bomb survivors and examined radiobiologically for compatability with other human and experimental data. The new doses show certain improvements over the original T65 doses. However, they suggest for chronic granulocytic leukemia, total malignancies, and chromosome aberrations, at neutron doses of 1 rad, RBEs in excess of 100, higher than expected from other findings. This and other indications suggest that either there are unrecognized systematic problems with the various radiobiological data, or the new doses are deficient in neutrons for Hiroshima, by a factor of about five. If in fact there were actually some 5-fold more dose from neutrons at Hiroshima than estimated by the new calculations, the RBEs would agree well with laboratory results, and other inconsistencies would largely disappear. Cancer risks are estimated for neutrons from the new doses and are compared with those estimated from radiobiologically reconciled doses (the new doses adjusted by adding approximately 5-fold more neutrons). The latter estimates appear more reasonable. For low-LET radiation, cancer risk estimates are altered very little by the new dose estimates for Nagasaki.

The nuclear criticality safety program at LLNL began in the 1950's with a critical measurements program which produced benchmark data until the late 1960's. This same time period saw the rapid development of computer technology useful for both computer modeling of fissile systems and for computer-aided management and display of the computational benchmark data. Database management grew in importance as the amount of information increased and as experimental programs were terminated. Within the criticality safety program at LLNL we began at that time to develop a computer library of benchmark data for validation of computer codes and cross sections. As part of this effort, we prepared a computer-based bibliography of criticality measurements on relatively simple systems. However, it is only now that some of these computer-based resources can be made available to the nuclear criticality safety community at large. This technology transfer is being accomplished by the DOE Technology Information System (TIS), a dedicated, advanced information system. The NCIS database is described.

It is planned to install 34,440 square feet of linear parabolic trough solar collectors at a new corrugator plant for making corrugated boxes. The system is to operate in parallel with a fossil fuel boiler. An assessment is presented of the impacts of the solar energy system on the existing environment and to determine whether or not a more detailed environmental impact statement is needed. The environmental assessment is based on actual operational data obtained on the collector, fluid, and heat transport system. A description of the design of the solar energy system and its application is given. Also included is a discussion of the location of the new plant in Fort Worth, Texas, and of the surrounding environment. Environmental impacts are discussed in detail, and alternatives to the solar industrial process steam retrofit application are offered. It is concluded that the overall benefits from the solar industrial process heat system outweigh any negative environmental factors. Benefits include reduced fossil fuel demand, with attending reductions in air pollutants. The selection of a stable heat transfer fluid with low toxicity and biodegradable qualities minimizes environmental damage due to fluid spills, personal exposure, and degradation byproducts. The collector is found to be …

Four Fe-based superalloys, JBK-75, Incoloy 903, Incoloy 905, and Incoloy 909 were evaluated as tube materials for ICCS Nb/sub 3/Sn superconductors. Evaluation consisted of 4-K tensile and elastic-plastic fracture-toughness testing, and a microstructural characterization of unwelded and autogenously gas-tungsten-arc welded sheet given a simulated postweld processing treatment of 15% cold reduction by rolling followed by a Nb/sub 3/Sn-reaction heat treatment of 96 hours at 700/sup 0/C plus 48 hours at 730/sup 0/C. Results indicate that JBK-75 and Incoloy 903 showed satisfactory combinations of strength and toughness for ICCS tube use requiring long Nb/sub 3/Sn-reaction heat treatments. Incoloy 905 welds and 909 showed unacceptable fracture toughness. Results are discussed in terms of microstructural changes caused by the extended Nb/sub 3/Sn-reaction heat treatment.