The initial phase of the Detroit Lakes Energy Systems Study was designed to assemble and analyze sufficient data from which to recommend specific classes of alternative energy supplies. Most of the information on meteorological conditions and biomass materials have been obtained. This is being compiled into a useful form for future evaluation. Research into legal and economic areas are underway. Analysis of this data is being conducted and results will be used in assessing the impact of alternative energy systems. Current technical information on solar thermal, solar photovoltaic, wind and hybrid power systems is being evaluated. Potential systems are being considered in light of their impact on the Detroit Lakes region and the northern latitudes in general. Final evaluation of the data is expected well within schedule.

This report oulines progress towards development of a high resolution, high throughput, curved crystal spectrometer suitable for line shape diagnostics of x-rays emitted from hot plasmas. The instrument is designed to interface with the MIT Tokamak (Alcator) with the initial aim of studying the prominent MoL lines which occur in the x-ray spectrum. However, it will have the versatility to function over an energy range of at least 1.5 keV to 7 keV allowing determination of temperature, charge state and density distributions for important impurity ions. The spectrometer employs a large, cylindrically bent crystal which focuses the dispersed x-rays along the cylinder axis where they are recorded by a position sensitive proportional counter. Thus, a wide energy range of the spectrum can be recorded simultaneously and sensitively from a short duration plasma. Computer control of data acquisition and analysis will allow real-time diagnostics.

A high pressure, supersonic, radio frequency discharge nozzle beam source was developed for the production of intense beams of ground state oxygen atoms. An efficient impedance matching scheme was devised for coupling the radio frequency power to the plasma as a function of both gas pressure and composition. Techniques for localizing the discharge directly behind the orifice of a water-cooled quartz nozzle were also developed. The above combine to yield an atomic oxygen beam source which produces high molecular dissociation in oxygen seeded rare gas mixtures at total pressures up to 200 torr: 80 to 90% dissociation for oxygen/argon mixtures and 60 to 70% for oxygen/helium mixtures. Atomic oxygen intensities are found to be greater than 10/sup 17/ atom sr/sup -1/ sec/sup -1/. A brief discussion of the reaction dynamics of 0 + IC1 ..-->.. I0 + C1 is also presented. 12 references.

Thermal energy is usually stored in energy storage systems as sensible heat at temperatures well above the ambient temperature. Most energy storage systems of this type suffer from two drawbacks: (1) the thermal losses to the surroundings are large, and (2) the energy is only available for recovery at the bulk temperature of the storage material; therefore, the stored energy can only be partially recovered. If the energy could be stored at near ambient temperature and recovered at the desired use temperature, thermal losses can be minimized and a high degree of efficiency can be maintained. The purpose of the program is to develop an energy storage system that accepts thermal energy at high temperatures, stores that energy at ambient temperature, and recovers the energy at the original high temperature. The energy is stored as chemical energy. The concept consists of storage and subsequent extraction of the heat of reaction from a pair of ammoniated salts near equilibrium conditions. By shifting the equilibrium in the forward or reverse direction, the heat of reaction can be stored or recovered. The system can be used for many different applications (i.e., different temperature levels) by selecting the appropriate salt pair for the high …

The purpose of this report is to set forth seismic criteria and design concepts applicable to review analyses and upgrading for selected nuclear power plants, although the principles are applicable generally to older operating plants. At the outset, it is expected that the review process would consist of two general tasks, one pertaining to detailed review of the existing plant in the light of applicable review criteria and the second involving detailed design and analysis studies to develop the desired (and possible) upgrading of the seismic resistance. It is envisioned that the detailed review would encompass inspection of the plant, review of existing documentation (reports, plans, and calculations) as appropriate with identification of those systems which realistically and economically are amenable to upgrading. As a part of this review it may be desirable to carry out a risk analysis to help provide a basis for the decisions that must be made as to the desirability and advantages of carrying out the upgrading.

The basic principles of the Engel-Brewer theory of metals are summarized and illustrated. Definitions of words used to describe its fundamentals are clarified. The theory predicts the extreme stability of the Lewis-acid-base alloys. The thermodynamics of such alloys may be obtained through the use of oxide-electrolyte, electrochemical cells. Experimental techniques associated with the use of these cells are explained in detail. Much attention is given to the preparation and processing of the materials required. A selective review of the cell literature demonstrates frequent difficulty in obtaining accurate thermodynamic data. In an attempt to correct this situation, as well as to correct problems discovered in this work, the physical processes which create the cell emf are clearly identified. The fundamental understanding afforded by the resulting cell model implies the procedures used to both discover and eliminate errors. Those due to concentration overpotentials, reactive impurities in the gas phase, and interfacial reactions are carefully analyzed. The procedures used to test for and attain equilibrium in an alloy-oxide, powder compact are supported through identification of the transport processes that mediate equilibration.

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.

Radio-tagged white sturgeon, 12 with temperature sensing transmitters, were monitored, from April through December 1977 in the free-flowing Hanford Reach of the Columbia River. River temperatures appeared to influence diel and seasonal sturgeon movements. In summer, from late afternoon to late evening, sturgeon environmental temperatures were higher than main current river temperatures. Sturgeon position determinations suggested movements into warmer inshore areas as darkness approached, perhaps to feed. After midnight, recorded sturgeon environmental temperatures declined, indicating movements back to cooler, main channel areas, especially after sunrise. Movements farther than 2 km from release sites did, not occur unless water temperatures were above 13{degrees}C.

A detailed electrical resistivity survey of 54 line-km was completed at the Coso Hot Springs KGRA in September 1977. This survey has defined a bedrock resistivity low at least 4 sq mi (10 sq km) in extent associated with the geothermal system at Coso. The boundaries of this low are generally well defined to the north and west but not as well to the south where an approximate southern limit has been determined. The bedrock resistivity low merges with an observed resistivity low over gravel fill east of Coso Hot Springs. A complex horizontal and vertical resistivity structure of the surveyed area has been defined which precludes the use of layered-earth or two-dimensional interpretive models for much of the surveyed area. In general the survey data indicate that a 10 to 20 ohm-meter zone extends from near surface to a depth greater than 750 meters within the geothermal system. This zone is bordered to the north and west by bedrock resistivities greater than 200 ohm-meters and to the south by bedrock resistivities greater than 50 ohm-meters. A combination of observed increases in: (1) fracture density (higher permeability), (2) alteration (high clay content), and (3) temperatures (higher dissolved solid content of …

Miscible-liquid displacements of water/ethanol solutions were conducted in a 2.54-cm-ID column packed with glass beads of 275 to 300 and 25 to 30 mesh with bed heights of 6.35 to 40.8 cm. The viscosity ratio of the resident fluid to displacing fluid was maintained at 0.72 for fluid pairs with favorable density differences. Dispersion coefficients obtained from a two-parameter model increased from approx.3 x 10/sup -5/ to approx.2 x 10/sup -2/ cm/sup 2//s with increasing packing particle size, fluid velocity, and density difference.

Element F03-01 was a so-called high-rhodium driver element centrally located within core 2 adjacent to a ''type 2'' control rod. Although not instrumented, the element was estimated to have operated at significantly higher temperatures than the majority of the driver elements and, therefore, was expected to exhibit enhanced release and migration of fission products from the fuel into its graphite components. Because of these expectations, the examination of element F03-01 was believed to be especially important. The element received an equivalent of 897 full-power days of irradiation prior to scheduled termination of core operation. The examination procedures emphasized the determination of radionuclide distributions in the graphite portions of the fuel element. Axial gamma scans indicated 36 Ci of /sup 137/Cs in the sleeve of the element and 9.8 Ci in the spine. From similar measurements, 358 Ci of /sup 137/Cs was estimated to be in the fuel, showing that approximately 13% of it was found in the graphite components. Axial distributions also indicated that significant amounts of the total inventory of /sup 137/Cs moved toward the bottom of the element during operation. The axial distribution of /sup 134/Cs was similar to that of /sup 137/Cs. Other nuclides found in the …

This synopsis provides the available data concerning the logging models at the DoE-Grand Junction facility, to date (1976). Because gamma-ray logs are used in uranium exploration to estimate the grade (percent U/sub 3/O/sub 8/) and the thickness of uranium ore zones in exploration drill holes, logging models are required to calibrate the gamma-ray logging equipment in order to obtain accuracy, uniformity, standardization, and repeatability during logging. This quality control is essential for accurate ore reserve calculations and for estimates of ore potential. The logging models at the DoE-Grand Junction facility are available for use by private industry in calibrating their gamma-ray logging equipment. 21 figures, 26 tables.

The principal techniques employed in obtaining, through momentum space integrations, double folded potentials for the analysis of nucleus--nucleus interactions are summarized. The primary emphasis is on numerical accuracy; therefore, no significant effort was made to minimize computer time other than to cast the problem in momentum space. The code RHOQ obtains the density distributions in momentum space, while FINRAN utilizes these results along with a nucleon--nucleon interaction in momentum space to obtain the local double folded potential in coordinate space.

Maps show drilling plans in four areas of the the Silver Cliff Mine in Lusk, Wyoming.

The DT fusion neutron irradiation of eleven BNL-LASL superconductor wires, six LASL Spinel, Al/sub 2/O/sub 3/, and YAG crystals (two of each), six NRL five 9's crystalline, tetragonal GeO/sub 2/ samples and four LASL-IIT high purity single crystals (MgO, YAG, Spinel and Al/sub 2/O/sub 3/) is described. The sample position, beam-on time and neutron dose record are given. The maximum neutron fluence on any sample was 1.87 x 10/sup 16/ neutrons/cm/sup 2/.

The DT fusion neutron irradiation of eleven BNL-LAST superconductor wires, six NRL GeO/sub 2/ crystals, two YAG, two Spinel and two Al/sub 2/O/sub 3/ crystals for LASL and four LASL high purity single crystals of MgO, YAG, Spinel and Al/sub 2/O/sub 3/ is described. The sample position, beam-on time, and neutron dose record are given. The maximum fluence on any sample was 1.51 x 10/sup 16/ neutrons/cm/sup 2/.

The DT fusion neutron irradiation of two LLL NbTi superconductor wires at 4.2/sup 0/K and 14 University of Oxford Cu/sub 3/Au TEM specimens at room temperature is described. The sample position, beam-on time, and neutron dose record are given. The results from four profile dosimetry foils measuring the lateral variation in neutron flux are given.

The DT fusion neutron irradiation of February 13 to 17, 1978 is briefly outlined by the neutron dose record and the neutron fluences on 19 dosimetry foils.

The DT fusion neutron irradiation of nine LLL stainless steel tensile specimens is described. The sample position, beam-on time and dose record are given. The maximum neutron fluence on any sample was 2.20 x 10/sup 17/ neutrons/cm/sup 2/.

Crack initiation and growth in the Charpy V-notch test are investigated for controlled deflections of the specimen applied both by slow bending and by impact. Charpy test specimens were deformed to various deflections, heat-tinted to mark the crack extensions, and broken apart at low temperature to allow measurement of the crack extensions. These measurements provide estimates of crack initiation as defined by various criteria. The loading point at which crack initiation occurs depends on the particular definition being used for ''initiation,'' but in all cases it is well before the maximum load is reached. When initiation is defined as the first observable micro-initiation away from the ductile blunting of the notch root, the experimental results are in good agreement with computer modeling predictions.

The objective of this study is to determine the extent to which the shocks and vibrations experienced by radioactive material shipping packages during normal transport conditions are influenced by, or are sensitive to, various structural parameters of the transport system (i.e., package, package supports, and vehicle). The purpose of this effort is to identify those parameters that significantly affect the normal shock and vibration environments so as to provide the basis for determining the forces transmitted to radioactive material packages. Determination of these forces will provide the input data necessary for a broad range of package-tiedown structural assessments. This is the first quarterly report on this work.

Tritium released in an enclosure tends to penetrate into the wall, and subsequent outgassing hampers the cleanup operation. Diffusion theory predicts that concentration and outgassing rate for an impulse release will follow a t/sup -3/2/ power-law decay at large time, in contrast to exponential decay for an impermeable wall and t/sup -1/2/ decay for an initially-saturated wall. Experiments carried out with ordinary and tritiated water in a polymeric enclosure confirm the diffusion theory, as do data on tritium gas outgassing from painted surfaces. Two lumped parameters are important: a flow parameter and a diffusion parameter. The diffusion parameter includes the diffusivity-solubility term DS/sup 2/. If DS/sup 2/ is large, the diffusion tail will depart earlier from exponential decay. DS/sup 2/ can vary widely, and will be especially large for tritiated water in polymeric materials.

This report is a compilation of abstracts of papers, internal reports, and talks presented during 1977 at national and international meetings by members of the Earth Sciences Division, Lawrence Livermore Laboratory. It is arranged alphabetically by author and includes a cross-reference by subject indicating the areas of research interest of the Earth Sciences Division.

Subassembly XX08 is a fueled and instrumented subassembly designed primarily for an ongoing program to investigate the thermal-hydraulic core environment within EBR-II under normal and off-normal plant operating conditions. XX08 contains 58-xenon-tagged, EBR-II Mark-II driver-fuel elements. The Mark-II fuel is expected to provide XX08 with an irradiation lifetime three times as great as that attained with its predecessor, XX07, i.e., a 9 versus 2.9% burnup. A burnup of 9 at.% is equivalent to about 29,000 MWt dyays of EBR-II reactor operation, which corresponds to 11 reactor runs at 2700 MWd per run.