The results of analyses of the airborne gamma radiation and total magnetic field survey flown for the region identified as the Bozeman National Topographic Map NL12-8 are presented in Volume I and II of this report. The airborne data gathered are reduced by ground computer facilities to yield profile plots of the basic uranium, thorium, and potassium equivalent gamma radiation intensities, ratios of these intensities, aircraft altitude above the earth's surface, total gamma ray and earth's magnetic field intensity, correlated as a function of geologic units. The distribution of data within each geologic unit, for all surveyed map lines and tie lines, has been calculated and is included. Two sets of profiled data for each line are included with one set displaying the above-cited data. The second set includes only flight line magnetic field, temperature, pressure, altitude data plus magnetic field data as measured at a base station. A general description of the area, including descriptions of the various geologic units and the corresponding airborne data, is included also.

The kinetics of precipitation reactions in geothermal brines can be studied accurately only if the brine samples are collected and examined under anaerobic conditions and with minimum cooling. Apparatus and techniques were developed that achieve this for brine temperatures below 100/sup 0/C. The concentration of suspended solids is measured gravimetrically after filtration, and the concentration of dissolved silica is measured by atomic absorption spectrophotometry. Data from Woolsey No. 1 well of the Salton Sea Geothermal Field illustrate typical results of the procedures.

Flat plate chord tests are one experimental method used to investigate how fluid/structure interaction (FSI) effects modify the impulsive loading in nuclear reactor pressure suppression pools. This analytical study examines the applicability of using a flexible flat plate in an otherwise rigid shell to model dynamic pool wall response in a flexible shell pressure suppression torus. Bubble pressures varying by a factor of seven are used as input to two-dimensional finite-element models. Boundary response to various plate and shell thicknesses are compared on the basis of equivalent natural frequency. Results indicate the qualitative flat plate response compares well with the flexible shell but absolute pressures vary significantly and nonconservatively.

An automated system for the performance of ion-exchange chromatography with corrosive solvents has been built. It is LSI-II microcomputer controlled and is capable of selecting six sample/solvents and collecting six separate fractions. Preliminary results on the separation of plutonium from 8M HNO/sub 3/ solutions indicate that the system can achieve chemical yields, analytical accuracy, and precision fully comparable to manual column operation at a considerable savings of operator time.

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The status of the following studies is given: calorimetry and thermodynamics of nuclear materials; americium recovery and purification; optimization of the cation exchange process for recovering americium and plutonium from molten net extraction residues; evaluation and comparison of bidentate extractants and methods for actinide recovery; a combined anion exchange-bidontate organophosphorus extraction process for molten salt extraction residues; a combined anion exchange-extraction chromatography technique for secondary recovery; plutonium recovery in the Advanced Size Reduction Facility; decontamination of Rocky Flats soil; separating lead and calcium from americium by chromate and oxalate precipitation; demonstration of the pyroredox process in the induction-heated, tilt-pour furnace; process development for recovery of americium from vacuum melt furnace crucibles; plutonium peroxide precipitation process; and a comparative study of annular and Raschig ring-filled tanks.

The conceptual design of a solar process steam system began with studies and evaluations of various alternative design configurations. From these evaluations a final candidate design configuration was selected which is to be used for further detailed analysis and engineering. An evaluation of various types of distributed collector systems is presented. Cost-effectiveness of various distributed collectors was determined on the basis of total relative cost (including foundation and installation) of the collector per square foot of collector surface for the same thermal output at noon. The considerations used to select the optimum site also are given. System optimization studies are presented, including a discussion of whether a storage facility should be provided. It was found that none is required. Three alternate system configurations are described, optimized, and compared and a final concept is selected in which water is partially boiled in the slat type collectors and steam is separated in a steam drum. A cost-effectiveness criterion based on the unit cost of net annual thermal energy generated was used in the optimization studies and is discussed. The impact of the system on the environment is assessed and a preliminary safety analysis is presented. (LEW)

Detailed estimates shown for the respective states are based largely on existing contracts and grants which are assumed to continue in 1980. Some DOE programs cannot be identified at the contractor level, and some elements of programs cannot be identified by states. These are listed in an Undesignated category. FY 1979 estimates are given; it is felt that Congressional actions on the FY 1980 budgets may affect the estimates shown.

A rapid and reliable method for analyzing technetium-99 in a wide variety of environmental samples, including waters, soils, stream sediments, and vegetations, has been developed. The procedure entails oxidizing the technitium to the heptavalent state and dissolving it in 6 N sulfuric acid. From that medium the technetium is quantitatively and selectively extracted into tributyl phosphate. A portion of the extract is then added to a scintillation cocktail, and technetium-99 activity is measured by liquid scintillation counting. Since a relatively large sample can be handled, the method can detest as little as 0.016 pCI /sup 99/Tc/ml water, 0.1 pCi /sup 99/Tc/g soil or sediment, and 0.2 pCi /sup 99/Tc/g vegetation. The procedure has also been adapted to analyzing urine samples, in which technetium activity as low as 0.12 pCi/ml can be detected.

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On the basis of time-integrated emittance measurements, several different types of field emitter diodes were characterized at 1 to 3 kA, 1 MeV. These measurements were part of the design effort for the injector system of a linear induction accelerator, to be used as a flash x-ray source at Lawrence Livermore Laboratory. The experimental parameters were the cathode type, the anode mesh texture, the diode spacing and voltage, and the level of collimation of the emerging beam. Experimental results are presented that show that over a wide range, the emittance was proportional to the level of collimation. For any one diode, with the spacing left fixed, the emittance was found to be essentially independent of the diode voltage and current. Differential focusing of different energy beam components affects most strongly the peripheral components of the beam, and strong collimation was found to minimize the effects of momentum spread on the emittance. The lowest emittances (30 to 40 mr-cm at 400 A) were obtained with a foil-type cathode in a ball-over-plane configuration, using an etched tungsten mesh anode, and collimating the beam to one quarter of the total current.

Sections of the 40-kV, 40-A, TMX source are shown. This module is comprised of the arc chamber and accelerator sections. The source accelerator section uses a single rectangular insulator to perform three functions: providing voltage standoff, forming the supporting structure, and acting as the vacuum wall. Both machinable glass ceramic (Corning Macor/sup TM/) and F.R.P. (Nema G-10) have been used for this insulater. In either case, the insulator is joined to the titanium base plate and extractor electrode by thermal-setting-epoxy adhesive. The parts are self jigging; the bonding is done at 120 to 130 /sup 0/C under a load of .34 MPa (50 psi).

Several methods for cleaning uranium samples prior to carbon analysis, using a Leco Carbon Analyzer, were evaluated. Use of Oakite Aluminum NST Cleaner followed by water and acetone rinse was found to be the best overall technique.

High-frequency electromagnetic probing is used to monitor the rate and direction of flow of fluids injected into the ground. This method shows the potential for providing more detailed information than procedures presently used. The experimental technique and the test-of-concept experimental results are discussed. This technique has applications in oil-reservoir engineering and in hydrology studies concerning storage of chemical and nuclear wastes. 11 figures.

Using a pair of lasers near 6000 A, the J = 6 ground state is excited to a J = 6 intermediate level and then to a J = 5 upper state. Non-resonant fluorescences from both excited states are separately detected. Results of a set of model calculations are tabulated. Level 3 average populations are always very small, since the system decays rapidly into inaccessible metastable states. This means that chemistry experiments are difficult. The differences between parallel and perpendicular polarization are modest. The fluorescence dips converge to a value near 50%. The level 3 populations do not approach a common value. This means that the most reliable experimental measurement does not determine the level populations. The most striking changes appear in the last two, most exact, models. The difference between the models is that one includes, for the first time, the linear frequency chirp produced by the fanlike spread of the focussed laser beams. This seemingly innocuous change halves the population left in the ground state. It appears that analogues of adiabatic passage and adiabatic rapid passage respectively are being observed.

Voitenko compressors are used to generate 43 mm/..mu..s air shocks in both a steel and a grout outlet pipe containing ambient atmospheric air. Fiber-optic ports provide diaphragm burst times, time-of-arrival (TOA) data, and velocities for the shock front along the 20-mm-ID exit pipes. Pressure profiles are obtained at higher enthalpy shock propagation than ever before and at many locations along the exit pipes. Numerous other electronic sensors and postshot observations are described, as well as experimental results. The primary objectives of the experiments are as follows: (1) provide a data base for normalization/improvement of existing finite-difference codes that describe high-energy air shocks and gas propagation; (2) obtain quantitative results on the relative attenuation effects of two very different wall materials for high-energy air shocks and gas flows. The extensive experimental results satisfy both objectives.

At the request of the Department of Energy, field techniques were developed to evaluate and improve the injection of brine into wells at Strategic Petroleum Reserve (SPR) sites. These wells are necessary for the disposal of saturated brine removed from salt domes where oil is being stored. The wells, which were accepting brine at 50 percent or less of their initial design rates, were impaired by saturated brine containing particulates that deposited on the sand face and in the geologic formation next to the wellbore. Corrosion of the brine-disposal pipelines and injection wells contributed to the impairment by adding significant amounts of particulates in the form of corrosion products. When tests were implemented at the SPR sites, it was found that the poor quality of injected brines was the primary cause of impaired injection; that granular-media filtration, when used with chemical pretreatment, is an effective method for removing particulates from hypersaline brine; that satisfactory injection-well performance can be attained with prefiltered brines; and that corrosion rates can be substantially reduced by oxygen-scavenging.

A comprehensive set of kerma factors for neutrons and photons has been computed for the International Commission on Radiological Protection's (ICRP) standard man, ICRP soft tissue, ICRP red bone marrow, ICRP eye lens, H/sub 2/O, dry air, Al, Si, /sup 32/S, Ar, and four thermoluminescent dosimeter materials. The energy range for neutrons is 10/sup -9/ to 20 MeV, divided into 175 energy groups. For photons, the energy range is 10/sup -3/ to 20 MeV, and kerma factors are calculated at 144 energy values. The kerma factors were computed using the neutron group-averaged and photon pointwise Evaluated Nuclear Data Library. Results are compared with those in other works where appropriate. The use of kerma factors to convert fluence to absorbed-dose index for ICRP tissue is discussed.

Leach rates for /sup 237/Np and /sup 239/Pu are investigated with a single-pass leaching system. The factorial experimental design uses several combinations of solution composition and flow rate, and two temperatures, 25 and 75/sup 0/C. The 25/sup 0/C results are compared with those from a modified IAEA procedure. At 25/sup 0/C, leach rates decrease with time. Agreement between results from the single-pass and modified IAEA methods is fair with WIPP brine leachant, good with NaHCO/sub 3/, and good with distilled H/sub 2/O. Leach rates are approximately independent of flow rates at room temperature, but increase with flow rates at high temperature. Rates for /sup 237/Np increase with temperature, but those for /sup 239/Pu either decrease or do not change with temperature. 7 figures.

A brief parametric survey of the x-ray characteristics of a gold micro-disk irradiated at 3 x 10/sup 14/ watt/cm/sup 2/ by a 1 nsec Nd-glass laser pulse has been provided as an example of a laser generated bright x-ray source. It was shown that a simple phenomenological model of the laser generated x-ray source as a microscopic equilibrium plasma radiating as a blackbody for a finite time determined by its hydrodynamic disassembly and radiation losses, serves to provide an adequate approximation to the x-ray characteristics of such sources. The current state of x-ray microscopy within the LLL laser fusion program was briefly reviewed. Kirpatrick--Baez grazing incidence reflection x-ray microscopes are being used to provide 3 to 5 ..mu..m resolution, broadband images (..delta..E/E approx. 0.3) over a spectral range from .6 keV to 3.5 keV. Zone Plate Coded Imaging is used to provide 5 to 10 ..mu..m resolution, broadband (..delta..E/E approx. 0.5) images over a spectral range from 3 keV to 50 keV. Efficient x-ray lensing elements with anticipated submicron resolution are being developed for narrowband (..delta..E/E approx. 10/sup -2/) imaging applications over a spectral range .1 keV to 8 keV. The x-ray lens design is that of a transmission blazed …

Gamma-ray spectroscopy measurements have been made on mixed uranium and plutonium oxides in sealed containers to determine the uranium and plutonium enrichment and isotopics. Experimental results obtained using two different methods were in good agreement with the known contents. The first method is applicable to thick samples of freshly reprocessed mixed oxide and determines isotopic abundances from measured absolute gamma-ray intensities. Measurement times depend on plutonium enrichment, but for mixed oxide enriched to 12% in plutonium, the fissionable content can be determined to better than 0.5% in 2 h. The second approach utilizes intensity ratios of selected pairs of gamma-rays to determine plutonium enrichment and uranium and plutonium isotopes. This method requires at least 12 h to determine the plutonium enrichment to an accuracy of 0.5%. However, it cannot be applied until the /sup 238/U daughter activities in the mixed oxide reach equilibrium, which requires at least 5 months after separation. Preliminary conclusions drawn from these two noninvasive and nondestructive measurement techniques, and recommendations for future experiments are discussed.

Energy-dispersive x-ray fluorescence analysis can be used for quantitative on-line monitoring of the product concentrations in single- or dual-element process streams in a reprocessing plant. The 122-keV gamma ray from /sup 57/Co is used to excite the K x-rays of uranium and/or plutonium in nitric acid solution streams. A collimated HPGe detector is used to measure the excited x-ray intensities. Net solution radioactivity may be measured by eclipsing the exciting radiation, or by measuring it simultaneously with a second detector. The technique is nondestructive and noninvasive, and is easily adapted directly to pipes containing the solution of interest. The dynamic range of the technique extends from below 1 to 500 g/l. Measurement times depend on concentration, but better than 1% counting statistics can be obtained in 100 s for 400 g/l concentrations, and in 1000 s for as little as 10 g/l. Calibration accuracies of 0.3% or better over the entire dynamic range can be achieved easily using carefully prepared standards. Computer-based analysis equipment allows concentration changes in flowing streams to be dynamically monitored. Changes in acid normality of the stream will affect the concentration determined, hence it must also be determined by measuring the intensity of a transmitted /sup …

Several nonlinear effects which limit Brillouin and Raman scatter of intense light in large underdense plasmas are examined. After briefly considering ion trapping and harmonic generation, we focus on the self-consistent ion heating which occurs as an integral part of the Brillouin scattering process. In the long-term nonlinear state, the ion wave amplitude is determined by damping on the heated ion tail which self-consistently forms. A simple model of the scatter is presented and compared with particle simulations. A similar model is also applied to Raman scatter and compared with simulations. Our calculations emphasize that modest tails on the electron distribution function can significantly limit instabilities involving electron plasma waves.

In an effort to upgrade outdated instrumentation and to take advantage of current and imminent technologies the Nuclear Chemistry Division at Lawrence Livermore Laboratory is about to undertake a major upgrade of their low level radiation counting and analysis facilities. It is expected that such a project will make a more coordinated data acquisition and data processing system, reduce manual data handling operations and speed up data processing throughput. Before taking on a systems design it is appropriate to establish a definition of the requirements of the facilities. This report examines why such a project is necessary in the context of the current and projected operations, needs, problems, risks and costs. The authors also address a functional specification as a prelude to a system design and the design constraints implicit in the systems implementation. Technical, operational and economic assessments establish necessary boundary conditions for this discussion. This report also establishes the environment in which the requirements definition may be considered valid. The validity of these analyses is contingent on known and projected technical, scientific and political conditions.