The use of combined dry/wet cooling systems for large base-load power plants offers the potential for significant water savings as compared to evaporatively cooled power plants and significant cost savings in comparison to dry cooled power plants. The results of a detailed engineering and cost study of one type of dry/wet cooling system are described. In the ''deluge'' dry/wet cooling method, a finned-tube heat exchanger is designed to operate in the dry mode up to a given ambient temperature. To avoid the degradation of performance for higher ambient temperatures, water (the delugeate) is distributed over a portion of the heat exchanger surface to enhance the cooling process by evaporation. The deluge system used in this study is termed the HOETERV system. The HOETERV deluge system uses a horizontal-tube, vertical-plate-finned heat exchanger. The delugeate is distributed at the top of the heat exchanger and is allowed to fall by gravity in a thin film on the face of the plate fin. Ammonia is used as the indirect heat transfer medium between the turbine exhaust steam and the ambient air. Steam is condensed by boiling ammonia in a condenser/reboiler. The ammonia is condensed in the heat exchanger by inducing airflow over the …

Initial results from a study of EUV emissions from the 2XIIB experiment are reported. Time-dependent brightness measurements of deuterium, oxygen, nitrogen, carbon and titanium emissions from the central 2XIIB plasma have been made. The deuterium Lyman alpha brightness is 1.5 x 10/sup 17/ photons sec/sup -1/cm/sup -2/sr/sup -1/. The Lyman alpha time development and broad spectral profile are consistent with other knowledge of the 2XIIB plasma. Oxygen is the dominant impurity in 2XIIB. The 0 VI 1032 A brightness is 1.65 x 10/sup 18/ photons sec/sup -1/cm/sup -2/sr/sup -1/. The oxygen concentration is 2% and its estimated confinement lifetime is 300 ..mu..s; this may imply mirror confinement of the oxygen ions. Nitrogen and carbon concentrations are 0.4% and 0.3%, respectively. It is not certain whether these impurities are mirror confined. The titanium concentration is believed to be low compared to that of oxygen. The power loss from the central plasma due to radiation by and ionization of light impurities is approximately 60 kW, which is 4% of the power deposited by the neutral beams. Further studies of impurity sources and penetration are now being performed.

Results from the initial phase of a study to establish subsurface design and operating criteria for a Compressed Air Energy Storage (CAES) facility are summarized. The primary objective was to derive a preliminary set of criteria that would help ensure the long term (30 to 40 year) integrity of CAES reservoirs in porous media, such as aquifers or abandoned natural gas reservoirs. In addition, appropriate research and development tasks were to be defined if the current technology was found to be inadequate. Preliminary stability and design criteria for storage of compressed air in porous media were determined on the basis of a survey of the open literature and the experience of experts in industry and universities. The results were separated into two categories: criteria for low temperature air injection (under 200/sup 0/F) and criteria for high temperature air injection (200 to 650/sup 0/F). Results are presented as maximum and/or minimum bounds for a number of parameters such as porosity, permeability, closure, storage pressure, caprock thickness, delta pressure, and caprock slope. One of the prime conclusions derived from an evaluation of the low temperature concept is that the technology currently exists to handle the potential design and operating problems. Therefore, there …

Eight conceptual deuterium-tritium fueled fusion power plant designs have been analyzed to identify waste sources, materials and quantities. All plant designs include the entire D-T fuel cycle within each plant. Wastes identified include radiation-damaged structural, moderating, and fertile materials; getter materials for removing corrosion products and other impurities from coolants; absorbents for removing tritium from ventilation air; getter materials for tritium recovery from fertile materials; vacuum pump oil and mercury sludge; failed equipment; decontamination wastes; and laundry waste. Radioactivity in these materials results primarily from neutron activation and from tritium contamination. For the designs analyzed annual radwaste volume was estimated to be 150 to 600 m/sup 3//GWe. This may be compared to 500 to 1300 m/sup 3//GWe estimated for the LMFBR fuel cycle. Major waste sources are replaced reactor structures and decontamination waste.

A survey of the industrial capabilities of the valve and valve-actuator industry to supply large, high-pressure stop valves for the future coal conversion industry is presented in this report. Also discussed are development and testing capabilities of valve and valve-actuator manufacturers and anticipated lead times required to manufacture advanced design valves for the most stringent service applications. Results indicate that the valve and valve-actuator industry is capable of manufacturing in quantity equipment of the size and for the pressure and temperature ranges which would be required in the coal conversion industry. Valve manufacturers do not, however, have sufficient product application experience to predict the continuing functional ability of valves used for lock-hopper feeders, slurry feeders, and slag-char letdown service. Developmental and testing efforts to modify existing valve designs or to develop new valve concepts for these applications were estimated to range from 1 to 6 years. A testing facility to simulate actuation of critical valves under service conditions would be beneficial.

Data indicate that possible uranium host rocks include the Precambrian rocks, the Ordovician Bat Cave Formation and Cable Canyon Sandstone, the Permian Abo Formation, Lower Cretaceous Dakota Sandstone, and the Upper Cretaceous-lower Tertiary McRae Formation. The Cenozoic sequence contains possible host beds; little is known, however, about its stratigraphy. Secondary uranium mineralization is found associated with faults in the Jornada area. All fault zones there are possible sites for uranium deposition. Possible sources for uranium in the Jornada del Muerto area include uraniferous Precambrian rocks, tuffaceous beds in the McRae Formation, and the Tertiary Datil and Thurman Formations. Hydrothermal solutions may have deposited the veinlike fluorite deposits, of which the purple varieties were found to be radioactive during this study.

This report is a comprehensive, multidisciplinary review of the health and environmental effects of cadmium and specific cadmium derivatives. More than 500 references are cited. The cadmium body burden in animals and humans results mainly from the diet. In the United States, the normal intake of cadmium for adult humans is estimated at about 50 ..mu..g per day. Tobacco smoke is a significant additional source of cadmium exposure. The kidneys and liver together contain about 50% of the total cadmium body burden. Acute cadmium poisoning is primarily an occupational problem, generally from inhalation of cadmium fumes or dusts. In the general population, incidents of acute poisoning by inhaled or ingested cadmium or its compounds are relatively rare. The kidney is the primary target organ for toxicity from prolonged low-level exposure to cadmium. No causal relationship has been established between cadmium exposure and human cancer, although a possible link between cadmium and prostate cancer has been indicated. Cadmium has been shown to be teratogenic in rats, hamsters, and mice, but no such effects have been proven in humans. Cadmium has been reported to increase the frequency of chromosomal aberrations in cultured Chinese hamster ovary cells and in human peripheral leukocytes. The …

Techniques for producing intense negative ion beams are discussed. These beams are required for intense neutral beam development at energies greater than 150 keV. Handling, acceleration, and stripping of negative ion beams are described.

An iterative refinement process for adjusting derivative values in the Hermite representation of a piecewise cubic function to produce visually pleasing interpolants is described. The difficulties encountered at various stages in the development of the algorithm are outlined, and future research directions are indicated. 22 figures.

A Monte Carlo mathematical model tracks the movement of fish in a body of water (e.g., a pond or reservoir) which is represented by a two-dimensional grid. For the case of a long, narrow reservoir, depth and length along the reservoir are the logical choices for coordinate axes. In the model, it is assumed that the movement of fish is influenced by gradients of temperature and dissolved oxygen, as well as food availability and habitat preference. The fish takes one spatial ''step'' at a time, the direction being randomly selected, but also biased by the above factors. In trial simulations, a large number of simulated fish were allowed to distribute themselves in a hypothetical body of water. Assuming only temperature was influencing the movements of the fish, the resultant distributions are compared with experimental data on temperature preferences.

A detailed survey of the present experimental situation in heavy-ion physics is presented. The discussion begins by considering the simple excitation of discrete states in elastic scattering, transfer, and compound-nucleus reactions; it then turns to more drastic perturbations of the nucleus high in the continuum through fusion, fission, and deeply inelastic scattering, and concludes with the (possibly) limiting asymptotic phenomena of relativistic heavy-ion collisions. 138 figures, 5 tables, 451 references. (RWR)

This conference covers various aspects of fossil-fuel power plants based on coal or coal-conversion products, as well as the process control equipment involved in the conversion or combustion processes.

From abstract: Results of a reconnaissance geochemical survey of the Plainview Quadrangle, Texas are reported. Field and laboratory data are presented for 969 groundwater samples and 571 stream sediment samples. Statistical and areal distributions of uranium and other possible uranium related variables are displayed. 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.

The LOFT Reactor Vessel 290/sup 0/ Downcomer Stalk Instrument Penetration Flange Stress Analysis has been completed using normal operational and blowdown loading. A linear elastic analysis was completed using simplified hand analysis techniques. The analysis was in accordance with the 1977 ASME Boiler and Pressure Vessel Code, Section III, for a Class 1 component. Loading included internal pressure, bolt preload, and thermal gradients due to normal operating and blowdown.

Appendix containing data on the recolonization of benthic macrofauna over a deep-water disposal site in the Duwamish River influenced portion of Elliott Bay. It accompanies a report on the chemical and physical effects of open-water disposal of dredged material from the Duwamish River into Elliot Bay as part of a study to determine the effects of disposal sites on organisms and the quality of surrounding water.

Development of a substitute potting compound developed by Pantex to replace the no longer available Dow Corning 93-119 is described. The specific approach taken in this development utilized Dow Corning Sylgard 184 as the basic starting material, altering its viscosity with Dow Corning Dielectric Gel Q3-6527 and then modifying the cure rate with Dow Corning Accelerator Q3-6559. Various tests were run to characterize both chemical and physical properties of the substitutes as well as the initial 93-119 and the starting raw materials. Summaries of the data peculiar to this substitute are presented here whereas a more detailed examination of the test methods and results for the overall project are presented in another report. The properties of two substitutes developed from the two extremes of viscosity to be expected for Sylgard 184 during production are presented. These substitutes are easily quick-frozen in the catalyzed state for production use upon thawing. They are however somewhat more difficult to deaerate and eventually cure to a harder state than the original DC 93-119.

This report describes the engineering, feasibility, economics, and environmental aspects of exploitation of Chattanooga Shale to recover U, synthetic crude oil, and byproduct Th, NH/sub 3/, S, Mo, V, Ni, and Co. It is concluded that the shale is a potential source of U, energy, and byproduct metals. This volume of the report covers the engineering description, feasibility, and economics of exploitation of the shale. (DLC)

A detailed dynamic analysis of the LOFT reactor core support structures was performed to determine the ability of the flow skirt/core filler and hold-down springs to withstand Loss-of-Coolant Accident (LOCA) plus Safe Shutdown Earthquake (SSE) loadings. A double-ended offset shear occurring in 15 msec (5 msec break time + msec for offset to occur) in the intact loop at the reactor vessel nozzle provided the basis for LOCA loads. The flow skirt/core filler and lower core support structure separate from the core barrel approximately 0.068 in. as a result of the hot leg LOCA. This small displacement and the resulting impact loads produce stresses in the springs, core barrel, flow skirt/core filler, and shear pins within allowables as specified in Section III of the ASME Code for faulted conditions.

The 35 papers presented are compiled and individual abstracts were prepared for selected papers. (JSR)

From preface: "This report summarizes the results of a comprehensive investigation of the impact of open-water dredged material disposal by barges in Elliot Bay, a portion of Puget Sound Estuary, Washington."

This product identification file was compiled as an aid to the industrial hygienist who may encounter the products listed in surveys for and studies of occupational health hazards. It is pointed out that the chemical composition of a product may vary from year to year and some components may be added or deleted without an indication on the label. Some of the data in this file may not be complete depending on the analysis requested. For example, a solvent may be the only component for which the product was analyzed. The file is arranged by listing the chemical manufacturer, followed by the trade name. In cases where no manufacturer is known, the trade name appears in alphabetical order. The log number and the chemist who analyzed the product are listed for reference.

Regional gravity data were collected in portions of the Pavant Range, Tushar Mountains, northern Sevier Plateau, the Antelope Range, and throughout Sevier Valley approximately between the towns of Richfield and Junction, Utah. Additionally, detailed gravity and ground magnetic data were collected in the vicinity of hot springs in both the Monroe and Joseph Known Geothermal Resource Areas (KGRA's) and subsurface geologic models were constructed. The regional gravity data were terrain corrected out to a distance of 167 km from the station and 948 gravity station values were compiled into a complete Bouguer gravity anomaly map of the survey area. This map shows a strong correlation with most structural features mapped in the survey area. Four regional gravity profiles were modeled using two-dimensional formerd and inverse algorithms.

Fourteen papers were represented by abstracts only and are listed by title. Separate abstracts were prepared for seventeen. (MHR)

The effect of the initial gas volume in the LOFT accumulators on the time to start of core reflood, after a LOCA, has been studied. The bases of the calculations are the data used and results presented in the Safety Analysis Report, Rev.1, August 1977, and the data in the RELAP and TOODEE2 program input and output listings. The results of this study show that an initial nitrogen volume of 12 cu ft, or more (at 600 psig initial pressure), would cause start of core reflood in time to prevent the cladding temperature from reaching 2200/sup 0/F. The 12 cu ft initial volume will expand from 600 psig, initial pressure, to about 10 psig (containment pressure shortly after start of LOCA is approximately 8 psig) when all ECC liquid has been expelled from the accumulator. This pressure margin is considered too small; the ECC flowrate will be zero before the accumulator is empty.