This talk is a review of results which have been reported during the past year on charmed particle decays in emulsions.

Twenty-six papers are presented on a variety of topics including: energy and transportaton facts and figures; long-range planning under energy constraints; technology assessment of alternative fuels; energy efficiency of intercity passenger and freight movement; energy efficiency of intracity passenger movement; federal role; electrification of railroads; energy impact of the electric car in an urban enviroment; research needs and projects in progress--federal viewpoint; research needs in transportation energy conservation--data needs; and energy intensity of various transportation modes--an overview. A separate abstract was prepared for each of the papers for inclusion in Energy Research Abstracts (ERA) and in Energy Abstracts for Policy Analysis (EAPA).

The explosion potential of the test cryopump became a paramount issue in the safety analysis required for the reactor experiment. The administrative limit for loading of the cryopump with normal hydrogen or deuterium is that amount of gas which will produce a partial pressure of 13 torr at a total pressure of 1 atmosphere, i.e., a 1.7% mixture by volume. At atmospheric pressure, combustion can occur for mixtures in the range 4.0 to 75%. It is important to know whether, in a leak-up-to-air accident, when the partial pressure will range from 100% to 1.7%, an explosion can occur. For the test cryopump (250l), loaded to the administrative limit, the energy of combustion would amount to 9.21 x 10/sup 5/ J, or 21.9 g of T.N.T. equivalent. However, for a TFTR beamline (73,000l), the corresponding numbers are 2.69 x 10/sup 7/ J, or 6.39 x 10/sup 3/ g of T.N.T. equivalent.

The linear-geometry magnetic confinement concept is among the oldest used in the study of high-temperature plasmas. However, it has generally been discounted as a suitable approach for demonstrating controlled thermonuclear fusion because rapid losses from the plasma column ends necessitate very long devices. Further, the losses and how to overcome them have not yet received parametric experimental study, nor do facilities exist with which such definitive experiments could be performed. Nonetheless, the important positive attribute, simplicity, together with the appearance of several ideas for reducing end losses have provided motivation for continued research on linear magnetic fusion (LMF). These motivations led to the LMF workshop, held in Seattle, March 9--11, 1977, which explored the potential of LMF as an alternate approach to fusion. A broad range of LMF aspects were addressed, including radial and axial losses, stability and equilibrium, heating, technology, and reactor considerations. The conclusions drawn at the workshop are summarized.

This paper presents and compares the design and fabrication of the FFTF and CRBRP reactor structures which support and restrain the reactor core assemblies. The fabrication of the core support structure (CSS) for the FFTF reactor was completed October 1972 and this paper discusses how the fabrication problems encountered with the FFTF were avoided in the subsequent design of the CRBR CSS. The radial core restraint structure of the FFTF was designed and fabricated such that an active system could replace the present passive system which is segmented and relies on the CSS core barrel for total structure integrity to maintain core geometry. The CRBR core restraint structure is designed for passive restraint only, and this paper discusses how the combined strengths of the restraint structure former rings and the CSS core barrel are utilized to maintain core geometry. Whereas the CSS for the FFTF interfaces directly with the reactor core assemblies, the CRBR CSS does not. A comparison is made on how intermediate structures in CRBR (inlet modules) provide the necessary design interfaces for supporting and providing flow distribution to the reactor core assemblies. A discussion is given on how the CRBR CSS satisfied the design requirements of the …

The lithium waterfall reactor is described as a concept in which liquid lithium serves as the coolant, tritium breeder, and 1st-wall and blanket structure protector. This reactor has emerged as a promising concept that alleviates the major problems associated with inertial confinement fusion systems. It eliminates the first wall problems resulting from x-rays and pellet debris, and minimizes cyclical thermal stresses. Also, the thick falling region of lithium attenuates neutrons to the point where the blanket structure could survive for the lifetime of the power plant at high power densities.

The fusion reactor neutral beam program consists principally of development and application of positive ion based systems in the energy range of less than or equal to 120 keV. Reactor studies for both mirrors and tokamaks, and even studies of tokamak research devices beyond TFTR, indicate a need for higher energies and also higher efficiencies than can be obtained by extrapolating positive ion based systems. The relative merits of systems based on positive ions, positive ions with energy recovery, negative ions and negative ions with energy recovery are reviewed. Then the neutral beam system parameters called for by mirror and tokamak design studies are reviewed. It is found that although certain types of reactors require more efficiency than others, increased emphasis on the development of negative ions and direct recovery is prudent in any case, and that there should be a test of ripple assisted injection into a tokamak.

Methodology and data bases are described which can provide a comprehensive planning assessment of the potential for geothermal district heating in any US market. This economic systems model encompasses life-cycle costing over a period of rising competitive fuel prices, it addresses the expansion and financing of a district system over time, and it includes an overall optimization of system design. The elemental area for all analyses is the census tract, for which published data allow estimation of residential and commercial heating demands, building retrofit requirements, and competitive fuel consumption and cost. A system type design, an appropriate hot water district piping system, and costing of heat supply is performed for groups of contiguous tracts in any urban market. Groups are aggregated, in decreasing benefit to cost order, to achieve optimal systems. A specific application for Salt Lake City, Utah, is also described.

The most important aspects of the Auxiliary System Testing Program to the overall startup of FFTF were in the areas of integrated testing of inerted cells, integrated leak rate testing of the containment building and testing of the waste gas processing systems for effluent cover gas and effluent cell atmosphere gases. The basic test methods and test results for these areas of the FFTF startup program are presented.

U.S. ERDA's research programs in fossil energy are reviewed with brief descriptions, budgets, etc. Of general interest are discussions related to the capabilities for such research of national laboratories, universities, energy centers, etc. Of necessity many items are treated briefly, but a general overview of the whole program is provided. (LTN)

A search for direct photon production has been performed at Fermilab in 200 and 300 GeV/c proton-Be interactions over a wide range of X/sub F/ and P/sub perpendicular to/. An excess of photons has been detected which when interpreted as single photon production yields a ..gamma../..pi../sup 0/ ratio which averages .070 +- .025 in the region 1.5 < p/sub perpendicular to/ < 4.0 GeV/c and -.7 < X/sub F/ < .0. This measurement is discussed and a comparison of this result with the ISR measurements of the ..gamma../..pi../sup 0/ ratio has been made in an attempt to infer the energy dependence of direct photon production.

The principles of limited-angle reconstruction of space-limited objects using the concepts of allowed cone and missing cone in Fourier space are discussed. The distortion of a point source resulting from setting the Fourier components in the missing cone to zero was calculated mathematically, and its bearing on the convergence of an iteration scheme involving Fourier transforms was analyzed in detail. It was found that the convergence rate is fairly insensitive to the position of the point source within the boundary of the object, apart from an edge effect that tends to enhance some parts of the boundary in reconstructing the object. Another iteration scheme involving Radon transforms was introduced and compared to the Fourier transform method in such areas as root mean square error, stability with respect to noise, and computer reconstruction time. 8 figures, 2 tables.

The neutral beam requirements for mirror reactors as presently envisioned are 200 keV for the Field Reversed Mirror (FRM) and 1200 keV for the Tandem Mirror (TMR). The hybrid version of the Standard Mirror, FRM and TMR require 100 to 120 keV. Due to the energy dependence of atomic processes, negative ions should produce neutrals more efficiently than positive ions above some energy and below this energy, positive ions are probably more efficient. This energy is probably somewhere between 100 and 150 keV for D/sup 0/, and 150 and 225 for T/sup 0/. Thus we conclude that hybrid reactors can use D/sup +/ ions but all of the fusion reactor designs call for D/sup -/ ions to make the neutral beams. Trends in the energy requirements are discussed. The hardening of neutral beams against neutron and gamma radiation is discussed.

The wet removal rate and wet deposition of pollutants is ultimately dependent upon the rate of pollutant attachment to the falling precipitation particles (hydrometeors) and to the precipitation flux at the ground. This attachment to the hydrometeors or collector particles is, in turn, dependent upon the physical characteristics of the pollutant. As expected, when considering wet removal, gases behave differently from aerosols. Modelers of gas scavenging (e.g., Hales 1972, Adamowitz 1979) stress the importance of drop size distribution, vertical gradients of gas concentration in the atmosphere and solubility in determining gas deposition at the surface. Aerosols, on the other hand, are removed at various rates depending upon aerosol size distribution, solubility, environmental humidity and age. Before the specifics of wet removal are dealt with, it is helpful to present some of the basic mathematical concepts used for treating problems in precipitation scavenging. By doing so, current terminology can be introduced and placed into a framework that should alleviate confusion about meaning. For example, a distinction between scavenging coefficients and simply scavenging will be made. The terminology in-cloud, below-cloud, washout, and rainout are shown to be ambiguous and will be dismissed. Other concepts, such as washout ratio, nucleation scavenging, vapor deposition …

The development of a general technique of analyzing well tests with variable flow rates is reported. The variable flow is approximated by a series of sequential straight line segments of arbitrary length and slope. (MHR)

The time projection chamber (TPC) is discussed. Its advantage is its ability to collect a great deal of information on multiparticle reactions from high-energy colliding beam experiments. The TPC makes it possible to reconstruct all the charged particles in the reaction, and it can be used for mass identification. (FS)

The first conference on advanced materials for alternative fuel capable directly fired heat engines was held at the Maine Maritime Academy, Castine, Maine. It was sponsored by the US Department of Energy, (Assistant Secretary for Fossil Energy) and the Electric Power Research Institute, (Division of Fossil Fuel and Advanced Systems). Forty-four papers from the proceedings have been entered into EDB and ERA and one also into EAPA; three had been entered previously from other sources. The papers are concerned with US DOE research programs in this area, coal gasification, coal liquefaction, gas turbines, fluidized-bed combustion and the materials used in these processes or equipments. The materials papers involve alloys, ceramics, coatings, cladding, etc., and the fabrication and materials listing of such materials and studies involving corrosion, erosion, deposition, etc. (LTN)

Structural design with brittle materials requires that the stress level in the component correspond to a material survival probability that exceeds the minimum survival probability permitted in that application. This can be achieved by developing failure models that fully account for the probability of fracture from defects within the material (including considerations of fracture statistics, fracture mechanics and stress analysis) coupled with non-destructive techniques that determine the size of the large extreme of critical defects. Approaches for obtaining the requisite information are described. The results provide implications for the microstructural design of failure resistant brittle materials by reducing the size of deleterious defects and enhancing the fracture toughness.

Sodium vapor deposits can affect reactor component operation and maintenance. Recorded cases include plugged cover gas lines and cementation of rotating components or sliding surfaces. Deposits found on plant scale components after testing in sodium were measured. Laboratory tests show the effect of Na pool temperature and condenser geometry on deposit accumulation rates and viewport fogging.

The status of research into collisions of nuclei at high energy is reviewed. Reactions and products are classified, and spectator matter is discussed. Then the thermalization of participant matter is considered at some length. Finally, disintegration of the hot matter is addressed. A = 20 and 40 projectiles of 250 to 1050 MeV/A are employed to illustrate the major points. 44 references, 10 figures. (RWR)

Separate abstracts are included for 20 of the 22 papers presented concerning innovative wind turbines which vary in design from the standard horizontal-axis propellor-type wind turbines. Two papers have been previously included in the data base.

The actinide borohydrides of Pa, Np, and Pu have been prepared and some of their physical and optical properties measured. X-ray powder diffraction photographs of Pa(BH/sub 4/)/sub 4/ have shown that it is isostructural to Th(BH/sub 4/)/sub 4/ and U(BH/sub 4/)/sub 4/. Np(BH/sub 4/)/sub 4/ and Pu(BH/sub 4/)/sub 4/ are much more volatile than the borohydrides of Th, Pa, and U and are liquids at room temperature. Results from low-temperature single-crystal x-ray diffraction investigation of Np(BH/sub 4/)/sub 4/ show that its structure is very similar to Zr(BH/sub 4/)/sub 4/. With the data from low-temperature infrared and Raman spectra, a normal coordinate analysis on Np(BH/sub 4/)/sub 4/ and Np(BD/sub 4/)/sub 4/ has been completed. EPR experiments on Np(BH/sub 4/)/sub 4//Zr(BH/sub 4/)/sub 4/ and Np(BD/sub 4/)/sub 4//Zr(BD/sub 4/)/sub 4/ have characterized the ground electronic state. 5 figures.

Radiation from high-power Q-switched lasers has been used recently in semiconductor research to anneal the lattice damage caused by ion implantation, diffuse surface-deposited dopant films, recrystallize doped amorphous films deposited on substrates, and remove precipitates present after conventional high-temperature dopant diffusion. All of these processes can be understood in terms of models based on macroscopic diffusion equations for heat and mass transport, cast in a finite-difference form to allow for the temperature- and spatial-dependence of the thermal conductivity, absorption coefficient, reflectivity, and other quantities. Results of calculations on silicon with the models show that the near-surface region of a sample can melt and stay molten for times of the order of 100 nsec during which dopant diffusion in the liquid state and nonequilibrium segregation during ultrarapid recrystallization are sufficient to explain the major features of the experimental results. Brief descriptions of the physical and mathematical models and some of the results obtained with them are given, with particular emphasis on segregation effects.

If spatially-averaged values of the beta ratio can reach 5 to 10% in tokamaks, as now seems likely, resistive toroidal-field coils may be advantageous for use in reactors intended for fusion-neutron applications. The present investigation has parameterized the design of steady-state water-cooled copper coils of rectangular cross section in order to maximize figures of merit such as the ratio of fusion neutron wall loading to coil power dissipation. Four design variations distinguished by different ohmic-heating coil configurations have been examined. For a wall loading of 0.5 MW/m/sub 2/, minimum TF-coil lifetime costs (including capital and electricity costs) are found to occur with coil masses in the range 2400 to 4400 tons, giving 200 to 250 MW of resistive dissipation, which is comparable with the total power drain of the other reactor subsystems.