Steady-state charge distributions are obtained for radioactive aerosol particles in bipolar ionized atmospheres with concentrations of 10/sup 2/ to 10/sup 8/ ions/cm/sup 3/. Ion--particle attachment is based on a diffusion--conduction model with unequal ion mobilities. Asymptotic formulas for charge distributions are derived from charge transfer rate equations. Cases include low and high specific activities with weak and strong electric fields. Mean charge and variance are obtained for Poisson and shifted Gaussian approximations in the appropriate cases. Comparisons are made with numerically calculated distributions.

This report is about the Clarification of LWR Dissolver Solutions.

General structure of the gauge group C underlying the unified weak and electromagnetic interactions, assuming that G is compact and that all quarks have only electric charges 2/3 and -1/3. Then, it is proven that G cannot contain any exceptional Lie groups G/sub 2/, F/sub 4/, E/sub 6/, E/sub 7/, and E/sub 8/ as its factor. Moreover, the underlying representations for quark multiplets to be used must be one of fundamental representations for each component simple Lie group contained as a factor of G. For example, only spinor representation is allowed for SO(2l + 1) groups. If G is semi-simple in addition, then G must be a product of SU(3l) groups. This latter fact is likely in conflict with the present experimental data.

For this reactor a reference case conceptual design was developed in some detail. The parameters of the design result partly from somewhat arbitrary physics assumptions and partly from optimization procedures. Two of the assumptions--that only 10% of the alpha-particle energy is deposited in the plasma and that particle confinement scales with the ion-ion collision time--may prove to be overly conservative. A number of possible start-up scenarios for the field-reversed plasmas were considered, but the choice of a specific start-up method for the conceptual design was deferred, pending experimental demonstration of one or more of the schemes in a mirror machine. Basic to our plasma model is the assumption that, once created, the plasma can be stably maintained by injection of a neutral-beam current sufficient to balance the particle-loss rate. The reference design is a multicell configuration with 11 field-reversed toroidal plasma layers arranged along the horizontal axis of a long-superconducting solenoid. Each plasma layer requires the injection of 3.6 MW of 200-keV deuterium and tritium, and produces 20 MW of fusion power. The reactor has a net electric output of 74 MWe. The preliminary estimate for the direct capital cost of the reference design is $1200/kWe. A balance-of-plant study is …

A method was developed that allows the mode-locking process to go to its steady state condition before the laser is Q-switched. This is done by pumping the laser quasi-cw for about 5 ms. During this time, the loss in the Q-switch is such that the laser will just slightly go above threshold. The active modulator is on during this time, and the laser oscillates quasi-cw for a period long enough to obtain stable transform-limited short pulses. At the end of this prelase period, the laser is Q-switched, and a train of stable, short pulses is obtained.

A series of runs was performed in which waste processing facility influent was spiked with americium-241, neptunium-237, and uranium-233 and run through the ultrafiltration and reverse osmosis (RO) units. The results of these experiments show that the ultrafiltration membranes are ionic dependent, whereas the RO unit is not. Membrane irradiation studies have been started. Continuous run parameters are being verified through a series of experiments. The small laboratory column tests were continued this quarter on several adsorbents. Decontamination factors were calculated for these adsorbents in removing neptunium-237 and americium-241 from waste solutions. Tests were continued with the 2-in. Engineering Columns using ultrafiltration product spiked with uranium-233. A 6-in. diameter column was installed in the combined raffinate line from the three Engineering Columns. This ''mixed bed'' column will polish the waste solution that is returned to the waste processing facility tanks. A quality control program was started this quarter.

Laser induced fusion is the forerunner of a class of inertial confinement schemes in which hydrogen isotopes are heated to thermonuclear conditions in a very short period. The process is characterized by such short time scales that fuel confinement is achieved through its' own finite mass and expansion velocity, approaching 1 ..mu..m/psec for ignition temperatures of order 10 keV (10/sup 8/ /sup 0/K). With current laser powers limited to several terrawatts one readily estimates, on the basis of energy conservation, target mass, and expansion velocity, that target size and laser pulse duration are on the order of 100 ..mu..m and 100 psec, respectively. Within these constraints, targets have been heated and confined to the point where thermonuclear conditions have been achieved. This paper describes a sampling of diagnostic techniques with requisite resolution (microns and picoseconds) to accurately describe the dynamics of a laser driven compression. As discussed in each case cited, these in turn provide insight to and quantitative measure of, the physical processes dominating the implosion. The success of the inertial confinement fusion program is strongly dependent on the continued development of such diagnostics and the understanding they provide.

Electron-beam braze welds were made in beryllium by using less than the recommended amount of aluminum filler metal. The welds exhibited a tendency to form microcracks prior to the termination of solidification; however, these microcracks were healed by the backfilling action of the aluminum/beryllium eutectic present in the fusion zone. Adverse effects attributable to the prior microcracking condition were not found.

Heating electrons by microwave power near either the electron cyclotron frequency or its harmonic is analyzed in some detail. The purpose of this study is to determine whether electrons in current or future mirror devices could be heated by electromagnetic waves in this frequency range. Absorption lengths, accessibility conditions, and appropriate polarization are among the concerns studied. It is found that the Tandem Mirror Experiment (TMX) may efficiently be heated by the extraordinary mode at omega = omega either in the solenoid-to-plug transition region or near the center of the plug at densities napprox. = 10/sup 13/cm/sup -3/.

Machining of the A106B GTA and EB welded specimens was completed. Laser welding of the AISI 304L and ASTM A106B materials is continuing. Tensile testing of the ASTM A106B EB welded specimens was initiated and completed. Testing of the ASTM A106B EB welded material indicated generally lower ductility than the parent material. Low-cycle fatigue testing of the ASTM A106B material in 13.8 MPa hydrogen indicates reductions in mean life of approximately 50 and 27% due to the GTA and EB welding respectively. (LK)

Two approaches were made to studies on genetic recombination in Chinese hamster cells: cytogenetics and the synthesis of a hybrid cell line containing two noncomplementing nutritional mutants, presumably in the same cistron, that can be used to detect crossing over to produce nutritional independence. The cytogenetic approach was used to characterize existing mutants and to study new mutants. It is also being used to characterize the parents of the hybrids and the hybrids themselves with a view that prototrophic recombinants selected biochemically will also show recombination cytologically. (HLW)

Today there exists in the United States a large volume of nuclear wastes that result from both military and commercial activities. The United States has to date placed major emphasis on disposal in only one rock type--salt--whereas other nations have considered other rock types, such as granite in England and Sweden and clays in Belgium. No comprehensive evaluation of isolation in rocks other than salt has been made in the United States, and it is most appropriate that other rock types be evaluated both for constructing disposal sites in areas devoid of salt and also for having alternative waste management plans in case substantial problems are encountered in using salt as a disposal medium. To evaluate the state-of-the-art, research needs, and research priorities related to waste disposal in largely-impermeable rocks, scientists and engineers working on geologic aspects of nuclear waste disposal were brought together. The Geotechnical Assessment and Instrumentation Needs (GAIN) Symposium for Nuclear Waste Isolation in Crystalline and Argillaceous Rocks was held July 16-20, 1978 in Berkeley. This report and recommendations are the proceedings from that symposium. The location, design, and testing of a potential nuclear waste disposal site are both a geologic and an engineering problem. Disposal requires …

The model is designed to predict the commercial-market penetration of various energy technologies in the industrial sector out to the year 2000. The model represents the refinement and further development of the Industrial Sector Model developed for the Market Oriented Program Planning Study task force in 1977. The model assesses the comparative economic competitiveness of each technology and then uses these assessments to project each technology's anticipated market penetration. The introductory chapter provides logic and special terminology information of the model. The next sections deal with the input requirements and a discussion of the solution of the model.

The Industrial Sector Technology Use Model provides a single framework for integrating all of the information and analysis into a set of predictions of industrial energy use. Given this volume of information which must be considered, this requires a set of computerized engineering-economic models. The design of these models is the subject of Chapter IV. The environmental factors in ISTUM are developed and presented in Chapter V. Chapter VI discusses the work accomplished by DATA Resources, Inc. in support of the ISTUM. A glossary, briefly defining special terms used in the ISTUM documentation, is given in Chapter VII. (MCW)

This volume, the second of a four-volume report, presents the current status of the Industrial Sector Technology Use Model (ISTUM), an analysis and projection of the use of energy in the industrial sector, developed as a tool to develop insights on the energy future of the US. Volume 1 describes the model logic and primary data inputs of ISTUM. This volume presents the results of the initial base case run of ISTUM. Volumes III and IV discuss in detail the energy demand data inputs and technology cost inputs, respectively. It is believed that, given the specified policy scenarios, the results presented in this volume provide an accurate picture of the trends in the demands for fuels and technologies for the remainder of the century. Following the introductory chapter, chapters are entitled: Projected Trends in Industrial Fuel Consumption; Projected Contributions of Technologies to the Industrial Sector; and Service Sector Perspectives of ISTUM 4/6/78 Base Case Results (steam sector, direct heat - intermediate and dirty; indirect heat - coal capable; machine drive service sector; electrolytic sector; space heat; indirect - not coal capable; calcining; glass melting; brick and clay firing; iron making; and steel reheating).

Appendix III-1 contains 4 sets of tables describing information included in the ISTUM demand base. The first set of tables describes 1974 fuel use: they disaggregate fuel consumption according to SIC, service sector, and fuel type. The next set show 1974 fuel consumption and service demand estimates and 1980, 1985, 1990, and 2000 service demand forecasts. The next set indicates, for each service sector, the fraction of an industry's service demands that are allocated to each size-load factor category. The last set of tables shows the quantities of service demand required by each service sector in 1974; these service demands are disaggregated by fuel type. Appendix III-2 describes in detail how ECDB energy consumption was mapped into ISTUM service sectors. Tables I and II summarize the ECDB to ISTUM translation. The remaining part of the appendix describes the sources and quantities of ISTUM service demand and fuel consumption estimates for each SIC-service sector combination. It briefly describes the sources of data on each industry (26) and give tables describing the industry's demand base. (MCW)

This volume of the 4-volume ISTUM documentation gives information on the individual technology specifications. The first chapter presents a general overview of the ISTUM technology data bases. It includes an explanation of the data-base printouts and how the separate-cost building blocks are combined to derive an aggregate-technology cost. The remaining chapters document the specific-technology-cost specifications. Boiler technologies (conventional coal steam, conventional natural gas and oil in the steam-service sector, black liquor and wood boilers, and space-heat service sector) and non-boiler conventional technologies (natural gas non-boiler, oil-fired non-boiler, coal-fired non-boiler technologies and non-boiler primary system costs) are covered in Chapter II. Chapter III, Fossil Energy Technologies, covers atmospheric fluidized-bed combustion, low-Btu gasification of coal, and medium-Btu gasification. Chapter IV, Cogeneration and Self-Generation Technologies, covers the steam service sector, machine-drive service sector, and electrolytic service sector. Solar and geothermal technologies (solar steam, solar space heat, and geothermal steam technologies) are covered in Chapter V, while Chapter VI covers conservation technologies. (MCW)

We have extended a simple, infinite-cloud, precipitation-mechanism model of thundercloud electrification to include effects due to the presence of radioactive aerosol particles. These effects involve ion generation, currents due to motions of ions and charged aerosol particles, and collection of ions and aerosol particles by hydrometeors and cloud droplets. Our conclusion is that an ion-pair generation rate G equal to or greater than 10/sup 12/m/sup -3/s/sup -1/ will prevent significant electric-field growth.

None

A stress analysis was performed on the LOFT Pressurizer Pressure Relief System to determine if it met the requirements of the ASME Boiler and Pressure Vessel Code, Section III, 1974 Edition, for Class 1 and Class 2 components. Deadweight, thermal expansion, seismic, design LOCE, and LOCA loads were considered. The results of this analysis indicate that the LOFT pressurizer pressure relief system will comply with Code specifications provided modifications are made to the hanger support configuration and one small section of pipe. The recommended changes are listed below. Note that some of these hangers were previously required based upon an analysis which subjected this same piping system to a reduced LOCE (20 millisecond valve opening). (1) Addition of Snubbers as per letter HIK-12-75, LOFT Pipe Hanger Requirements on Main Feed Main Steam Pressurizer and ECC Systems. (2) The 1/2'' Line 1/2''-PCS-10 between the tee and CVP-136-19 must be increased in diameter to 1.050 inches (OD of nominal 3/4'' pipe). (3) Modification of Unibals and flat bars as per letter Muff-2-76, required change of flat bar hangers and unibals on pressure relief and pressurizing piping. 9 refs., 6 figs., 1 tab.

The Savannah River Laboratory (SRL) is coordinating an interlaboratory effort to provide, test, and use state-of-the-art methods for calculating the environmental impact to an offsite population from the normal releases of radionuclides during the routine operation of a fuel-reprocessing plant. Results of this effort are the estimated doses to regional, continental, and global populations. Estimates are based upon operation of a hypothetical reprocessing plant at a site in the southeastern United States. The hypothetical plant will reprocess fuel used at a burn rate of 30 megawatts/metric ton and a burnup of 33,000 megawatt days/metric ton. All fuel will have been cooled for at least 365 days. The plant will have a 10 metric ton/day capacity and an assumed 3000 metric ton/year (82 percent online plant operation) output. Lifetime of the plant is assumed to be 40 years.

We have carried out conceptual design studies of fusion reactors based on the three current mirror confinement concepts: the standard mirror, the tandem mirror, and the field-reversed mirror. Recent studies of the standard mirror have emphasized its potential as a fusion-fission hybrid reactor, designed to produce fission fuel for fission reactors. We have designed a large commercial hybrid based on standard mirror confinement, and also a small pilot plant hybrid. Tandem mirror designs include a commercial 1000 MWe fusion power plant and a nearer term tandem mirror hybrid. Field-reversed mirror designs include a multicell commercial reactor producing 75 MWe and a single cell pilot plant.

A large, new Mirror Fusion Test Facility is under construction at LLL. Begun in FY78 it will be completed at the end of FY78 at a cost of $94.2M. This facility gives the mirror program the flexibility to explore mirror confinement principles at a signficant scale and advances the technology of large reactor-like devices. The role of MFTF in the LLL program is described here.

The hybrid reactor studies are reviewed. The optimization of the point design and work on a reference design are described. The status of the nuclear analysis of fast spectrum blankets, systems studies for fissile fuel producing hybrid reactor, and the mechanical design of the machine are reviewed. (MHR)