The contract objective is to complete the design and development actions that upgrade the 40-kW fuel cell power plant to a configuration suitable for on-site demonstration testing. The modifications will improve operating capability, durability and maintenance interval and lead to reduced production costs. Equipment to recover and use the by-product heat of electric generation will be available on the power plant for field verification of on-site heat recovery. The 40-kW power plant will be compatible with the power characteristics required for conventional heat pumps and conventional 60 Hz, 120/208 volts electrically operated equipment. Progress is reported. (WHK)

The Antares laser will require that about 100 high-precision NaCl windows of 18-in. diameter be produced, maintained, and repaired. To aid the industry in achieving the required production rates, a polishing development program was undertaken by LASL's Laser Division in collaboration with the Air Force and International Laser Systems. The design and initial shakedown of the polishing machine is described. Preliminary results indicate the machine's design is sound, its operation is generally simple, and it should be capable of finishing 18-in. NaCl to better than lambda/2 visible and 20-10 surface. Shakedown work with glass has demonstrated 0-0 surface, complete absence of edge roll, and lambda/16 over 12 in., and lambda/6 over 19 in.

A suitability of 6 packing materials for removal of sodium fire aerosols in a wet cell scrubber was evaluated experimentally by measuring the efficiency and flow resistance of two 10.2 cm deep cells in series at air face velocities of 185 and 289 cm/sec, water flow rates of 0.210 ad 0.387 cm/sup 3//sec/cm/sup 2/, with and without aerosol prehumidification. The most satisfactory material was found to be 50 ..mu..m diameter stainless steel fibers at a packing density of 30 kg/m/sup 3/ (porosity = 0.99). Two 10.2 cm deep cells in series gave a removal efficiency of 85% for typical sodium fire aerosols at a face velocity of 289 cm/sec. Measurement of efficency as a function of particle size indicated a reduction in efficiency in the 0.4 to 1.1 ..mu..m size range for all packing materials.

Results of work performed from July 1, 1978 through September 30, 1978 on the Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program are presented. Candidate alloys were evaluated for Very High Temperature Reactor Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the affect of simulated reactor primary coolant (Helium containing small amounts of various other gases), the high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. The activities associated with the characterization of the materials for the screening test program are reported, i.e., test specimen preparation, information from the materials characterization tests performed by General Electric, and the status of the simulated reactor helium supply system, testing equipment, and gas chemistry analysis instrumentation and equipment. The status of the data management system is presented.

Projections indicate that MJ/MW laser systems, operating with efficiencies in escess of 1 percent, are required to drive laser fusion power reactors. Moreover, a premium in pellet performance is anticipated as the wavelength of the driver laser system is decreased. Short wavelength laser systems based on atomic selenium (lambda = 0.49..mu..), terbium molcular vapors (0.55..mu..), thulium doped dielectric solids (0.46..mu..), and on pulse compressions of KrF excimer laser radiaton (0.27..mu..) have been proposed and studied for this purpose. The technological scalability and efficiency of each of these systems is examined in this paper. All of these systems are projected to meet minimum systems requirements. Amont them, the pulse-compressed KrF system is projected to have the highest potential efficiency (6%) and the widest range of systems design options.

The concept design for a small (less than 10 MWe) solar thermal electric generating plant was completed using projected 1985 technology. The systems requirements were defined and specified. The components, including an engineering prototype for one 15 kWe module of the generating plant, were conceptually designed. Significant features of the small solar thermal power plant were identified as the following: (1) 15-kWe Stirling-cycle engine/alternator with constant power output; (2) 10-meter point-focusing paraboloidal concentrator with cantilevered cellular glass reflecting panels; (3) primary heat pipe with 800/sup 0/C output solar cavity receiver; (4) secondary heat pipe with molten salt thermal energy storage unit; (5) electric energy transport system; and (6) advanced battery energy storage capability. The present emphasis for achieving cost reduction goals centers on improving conversion efficiency and reducing the cost of key components.

This report summarized studies performed since the last workshop meeting. The studies have been divided into four sections: (1) the relative response of Hankins-type albedo-neutron dosimeters made of cadmium and boron; (2) the effect of distance from the body on the response of albedo-neutron dosimeters; (3) the use of the ratio of the top to bottom TLDs to determine the calibration factor for albedo-neutron dosimeters; and (4) neutron survey at a power reactor and at a neutron radiography facility.

Seven chapters are included. Chapters 1 and 2 introduce the Alfven wave and describe its linear properties in a homogeneous medium. Chapters 3 and 4 cover the effects of inhomogeneities on these linear properties. Particular emphasis is placed on the appearance of a continuum spectrum and the associated absorption of the Alfven wave which arise due to the inhomogeneity. The explanation of the physical origin of absorption is given using kinetic theory. Chapter 5 is devoted to the associated plasma instabilities. Nonlinear effects discussed in Chapter 6 include quasilinear diffusion, decay, a solitary wave, and a modulational instability. The principles of Alfven wave heating, a design example and present-day experimental results are described in Chapter 7.

The stress corrosion susceptibility of Type 5083 aluminum--magnesium alloy in plate form and press-formed shapes was determined in the short transverse direction. C-ring type specimens were exposed to alternate immersion in a sodium chloride solution. The test equipment and procedure, with several innovative features, are described in detail. Statistical test results are listed for seven thermomechanical conditions. A certain processing scheme was shown to yield a work-strengthened part that is not sensitized with respect to stress corrosion cracking.

The significant economic data for the current production multiblade wafering and inner diameter slicing processes were tabulated and compared to data on the experimental and projected Varian multiblade slurry, STC ID diamond coated blade, Yasunaga multiwire slurry and Crystal Systems fixed abrasive multiwire slicing methods. Cost calculations were performed for current production processes and for 1982 and 1986 projected wafering techniques.

A generalized Eulerian method is described for analyzing the fluid transients and the structural response in nuclear reactors under the postulated accident conditions. The phenomena considered are the wave propagation, slug impact, sodium spillage, bubble migration, and the fluid-structure interaction. The basic equations and numerical formulation are presented in detail. Sample calculations are given to illustrate the analysis. It is shown from the results that the implicit, iterative method used is unconditionally stable and is especially suitable for problems involving large material distortions.

The removal of CO/sub 2/ from air in a calcium hydroxide slurry-agitated reactor was investigated to aid the design of such vessels. Gas-liquid interfacial areas were calculated using theoretical rate expression and experimental data at specific operating conditions. A correlation for interfacial areas was then determined as a function of impeller speed, impeller diameter, gas flow rate, and concentration of the slurry. Decontamination factors were also determined.

The main points, conclusions, products, and recommendations of this project are outlined briefly. (MHR)

The following appendices are included: summaries of conferences with solar data users; solar data user questionnaire and sample formats; evaluation of the solar data user questionnaire; remarks stimulated by the solar data user questionnaire; effects of solar data accuracy on the performance and economics of solar energy systems; summary of solar data measurements; reports of site visits to solar data measurement stations; data correction factors; the regionalization of California for solar monitoring; participants at the Solar Data Management Conference, 19 November 1976; and rehabilitation techniques for daily solar radiation data. (MHR)

Derivation of the governing equation, including temperature effects, is given where the permeability-viscosity ratio is assumed to be an arbitrary function of r{sup 2}t. This function is represented by a Fermi-Dirac function, whose parameters are determined based upon physical considerations. The solution for the pressure change is analytic except for the final step, where a numerical integration is called for. The results and implications of the calculations are discussed. Summary and concluding remarks are presented.

An analytic method is presented for determining the dilation of fast reactor fuel assembly ducts. For temperatures where creep is linearly dependent on stress, the method is rigorous in satisfying equilibrium, compatibility and stress-strain equations. Solutions are presented for two cases: (1) a duct with constant pressure differential, (2) a duct with varying pressure differential. Results are in close agreement with finite element results of the MARC-CDC program. The method is used to predict the dilation of the Fast Test Reactor (FTR) ducts under different operating conditions. Presented are the stress, strain and dilation predictions along the duct wall, and the duct dilation variations with its geometric and loading parameters.

Angular distributions of the analyzing powers, A/sub y/, A/sub xx/, A/sub yy/, and A/sub xz/ were measured and tabulated for the /sup 2/H(vector d,p)/sup 3/H reaction at deuteron lab energies of 13.39 and 17.00 MeV, and have observed that these distributions are not of the shapes expected for a simple direct-neutron-transfer reaction mechanism. Also measured and tabulated were the same four analyzing powers for both the /sup 2/H(vector d,p)/sup 3/H reaction and its charge-symmetric partner /sup 2/H(vector d,n)/sup 3/He at deuteron lab energies of 15.50 and 17.00 MeV in the c.m. angular range 80 to 130/sup 0/. These latter data were obtained by simultaneous detection of the tritons and/sup 3/He particles. No appreciable differences in the respective analyzing powers for the two reactions were observed, which is in cntrast to published work of others at lower energies. 17 references.

Data are presented from the radioanalysis of tissues collected from cattle and mule deer, desert bighorn sheep, feral horses, and other wildlife that resided on or near the Nevada Test Site during 1976. Other than the naturally occurring potassium-40, gamma-emitting radionuclides were detected infrequently with the exception of /sup 131/I in animal thyroid samples collected after September 25 (the date of a Chinese nuclear test). Strontium-90 concentrations in bones from deer, cattle, and desert bighorn sheep continued the downward trend of recent years. Tritium concentrations were generally within ambient limits with the exception of animals exposed to sources of contamination; e.g., Sedan Crater, drainage ponds from Area 12 tunnels, etc. Analysis of actinide in tissues was emphasized during 1976. Graphs illustrate the /sup 239/P levels in lungs, livers, and femurs from Nevada Test Site beef cattle for the years 1971 through 1976. Femur and lung residue data are nearly identical for each year with liver concentrations being a factor of 2 or 3 lower. Hypothetical dose estimates to man were calculated on the basis of the daily consumption of 0.5 kilogram of liver or muscle from animals that contained peak actinide levels. The highest postulated dose was 11 millirem from …

The APORT computer code was developed to apportion variables tabulated for polygon-structured civil districts onto cells of a polar grid. The apportionment is based on fractional overlap between the polygon and the grid cells. Centering the origin of the polar system at a pollutant source site yields results that are very useful for assessing and interpreting the effects of airborne pollutant dissemination. The APOPLT graphics code, which uses the same data set as APORT, provides a convenient visual display of the polygon structure and the extent of the polar grid. The APORT/APOPLT methodology was verified by application to county summaries of cattle population for counties surrounding the Oyster Creek, New Jersey, nuclear power plant. These numerical results, which were obtained using approximately 2-min computer time on an IBM System 360/91 computer, compare favorably to results of manual computations in both speed and accuracy.

An apparatus consisting of a vacuum ultramicrobalance and optical equipment for measuring transmittance and front surface reflectance of thin films from 400 to 800 nm is described. Thin films formed on substrates by thermal or reactive evaporation can be heated in reactive gases of different compositions and pressures. As the chemical composition of the film changes, the optical changes in the film can be monitored simultaneously using computerized data collection, control, and analysis. Representative results obtained for the preparation of a Cu/sub 1/ /sub 63/S film on a sapphire substrate and its reaction with oxygen are presented along with ion scattering profiles, SEM, and structural data taken after the film was removed from the microbalance.

The application of the Principal Components Analysis (PCA) methodology to the long-term assessment of operating releases from the nuclear power industry was investigated. Gaussian calculations had been previously compared with MATHEW/ADPIC calculations for a simulated 24-hr release in the Hudson River Valley and an area in the southeast. Considerable differences were noted in the comparisons, which were attributed to the more realistic simulation of the time and space varying wind fields by the MATHEW/ADPIC computer codes.

Possible impacts of an 800-MW coal-fired power plant to be built near Atikokan, Ontario were evaluated. It is feared that the emissions of SO/sub 2/ will lead to the deposition of sulfuric acid and result in the acidification of freshwaters in nearby parks and wilderness areas. The most obvious biological effects of acidification are damages to populations of fish. Less conspicuous but no less severe damages also occur to other organisms. It appears that all trophic levels are affected: species numbers are reduced, biomasses are altered, and primary production and decomposition are impaired. Field experiments and laboratory experiments indicate that microbial activity is reduced and that the recycling of materials is greatly impeded at low pH. This may interfere with nutrient supplies to plants and decrease the microbial biomass available to higher trophic levels. Phytoplankton densities decrease in acidified lakes and there is a reduction in some species of macrophytes. On the other hand, Sphagnum and benthic filamentous algae greatly increase in acidified conditions. The total primary productivity of lakes and streams may actually increase because of such dense growths on the bottom. Zooplankton and benthic invertebrate communities become less complex as acidity increases. This may in part be due …

This study involved an assessment of the potential economic benefit of small solar thermal electric power systems to small municipal and rural electric utilities. Five different solar thermal small power system configurations were considered in the study representing three different solar thermal technologies. The configurations included: (1) 1-MW, 2-MW, and 10-MW parabolic dish concentrators with a 15-kW heat engine mounted at the focal point of each dish. These systems utilized advanced battery energy storage. (2) A 10-MW system with variable slat concentrators and central steam Rankine energy conversion. This system utilized sensible thermal energy storage. (3) A 50-MW central receiver system consisting of a field of heliostats concentrating energy on a tower-mounted receiver and a central steam Rankine conversion system. This system also utilized sensible thermal storage. The approach used in determining the potential for solar thermal small power systems in the small utility market involved a comparison of the economics of power supply expansion plans for seven hypothetical small utilities through the year 2000 both with and without the solar thermal small power systems. Insolation typical of the Southwestern US was assumed. A comparison of the break-even capital costs with the range of plant costs estimated in this study …

Based on shipping assumptions and the current accident rate of 2.5 x 10/sup -6/ per mile, it is estimated that gasoline tank trucks will be involved in 1,781 accidents in 1980, and that 110 of the accidents (about one in 15) will result in a release of 3,000 gallons of gasoline or more from the tank truck. About one in four of the releases are expected to result in a large fire. The estimated number of fatalities from the gasoline releases in 1980 is 29, with 12 of these fatalities being drivers of gasoline tank trucks, and the other 17 being occupants of other vehicles involved in the accident. Fatalities of other members of the public were found to occur infrequently. An additional 26 persons are expected to be fatally injured from the accident forces, regardless of the hazardous nature of the cargo. These total fatality figures (55) were compared to the prediction of 43 deaths of the Bureau of Motor Carrier Safety.