The Linear Free Electron Laser is numerically analyzed in the one dimensional limit by following an average (resonant) particle. Several different wiggler schemes are presented, and electron beam current density requirements are discussed. A variable phase angle buncher is also proposed.

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.

Efforts of this task indicate that powerplant productivity is a complex issue that has to take into account economic factors, equipment limitations, and system-loading characteristics as well as external constraints such as regulatory requirements. Among the specific findings are: (1) utilities in Illinois use the industry-wide measures of performance such as capacity factor, availability factor, forced outage rates etc.; equivalent availability as a measure is not in common practice; (2) several unit performance statistics are collected on a routine basis such as the daily unit status, component outage data, monthly production figures etc.; (3) identifying major causes of lost productivity appears to be a relatively simple task, but finding economically and technically acceptable corrective actions are generally more difficult; (4) selection of improvement projects, as well as evaluating their future impacts, is mostly based on operating experience and engineering judgement, with no use of formal analytical/statistical models; (5) there generally is a group in every utility - typically called the power production department - with routine responsibilities for upkeep of unit productivity; and (6) recently the Commonwealth Edison Co. has developed a procedure for utilizing the Edison Electric Institute outage data base for analyzing productivity-related questions at nuclear plants; this …

A summary of total cumulative fuel consumption differences by fuel type through 1990 for four improvement scenarios is presented for Commonwealth Edison Company (CE) and for Illinois Power Company (IP). In all scenarios, liquid-fuel consumption is reduced. Generation is shifted to the coal and/or nuclear units for which improved availability has been assumed. For a 2% improvement in both planned (POR) and forced outage rates (FOR), a total of more than 16 million barrels of No. 6 oil will have been saved by 1990 by the two companies. This is the result of improving 10,894 MW on the CE system and 2234 MW on the IP system. For the two utilities combined, gross savings (in 1978 dollars) range from $83 million for a 1% POR improvement to $346 million for 2% improvements in both POR and FOR. In terms of their effect on ratepayers, these savings would be even greater since gross receipt taxes and other charges would be applied to a smaller-generation cost base under the improvement scenarios. Caution must be exercised however, since results do not take into consideration the costs of achieving the improved performance. The proportion of net benefits that would be passed on to ratepayers …

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)

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).

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.

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.

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.

This report disucsses the development of on-line state and parameter estimators used to analyze the structural response of buildings. The estimator/identifier is an extended Kalman filter (EKF), which has been applied with great success in other technological areas. It is shown that the EKF can perform quite well on simulated noisy structural response data.

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.

There are nine different systems requiring over fifty computers in the Local Control and Instrumentation System for the Mirror Fusion Test Facility. Each computer system consists of an LSI-11/2 processor with 32,000 words of memory, a serial driver that implements the CAMAC serial highway protocol. With this large number of systems it is important that as much software as possible be common to all systems. A serial communications system has been developed for data transfers between the LSI-11/2's and the supervisory computers. This system is based on the RS 232 C interface with modem control lines. Six modem control lines are used for hardware handshaking, which allows totally independent full duplex communications to occur. Odd parity on each byte and a 16-bit checksum are used to detect errors in transmission.

A single electrostatic wave in a magnetoplasma causes stochastic ion motion in several physically different situations. Various magnetic fields (uniform, tokamak, and mirror) and various propagation angles with respect to the field have been studied. A brief review of this work shows that all situations can be understood using the concept of overlapping resonances. Analytical calculations of the wave amplitude necessary for stochasticity have been carried out in some cases and compared with computer and laboratory experiments. In the case of an axisymmetric mirror field the calculations predict stochastic motion of ions with energy below a threshold that depends weakly on the wave amplitude and on the scale lengths of the magnetic field. Studies with an azimuthally asymmetric field show that the asymmetry causes substantial changes in the motion of some ions.

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.

To successfully develop the geothermal resources of the Imperial Valley, adequate supplies of cooling water must be obtained. The primary sources of water include waste waters from agricultural lands, condensate from flashed-steam facilities, and irrigation water. The major advantages and disadvantages of these supplies are examined and then the consequences of adopting six sets of water policies to support three scenarios of geothermal energy production are assessed. The assessment includes analyses of potential constraints to development as a result of restrictive water policies. It also includes predictions of changes in the Salton Sea's elevation and salinity caused by the consumption of agricultural drain water for cooling.

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.

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.

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.

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.

A design for water-cooled extractor grids for long-pulse and continuously operated ion sources for neutral-beam injectors is described. The most serious design problem encountered is that of minimizing the thermal deformation (bowing) of these slender grid rails, which have typical overall spans of 150 mm and diameters on the order of 1 mm. A unique U-tube design is proposed that offers the possibility of keeping the thermal bowing down to about 0.05 mm (about 2.0 mils). However, the design requires high-velocity cooling water at a Reynolds number of about 3 x 10/sup 4/ and an inlet pressure on the order of 4.67 x 10/sup 6/ Pa (677 psia) in order to keep the axial and circumferential temperature differences small enough to achieve the desired small thermal bowing. It appears possible to fabricate and assemble these U-tube grids out of molybdenum with high precision and with a reasonably small number of brazes.

The electric utility sector sub-model within PIES uses a number of modeling approximations in order to formulate the power plant dispatch in a linear programming framework. Several such modeling details were studied using a probabilistic dispatch model (PROMOD III) to quantify the error introduced by each. These tests indicate that PIES tends to significantly underpredict the consumption of high cost fuels (distillates, etc.) by the electric utility sector. Two adjustments to the PIES model are suggested as means of overcoming this problem.

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 …

The major objective of this program is to define and verify a process sequence for the fabrication of solar cell modules from dendritic web silicon. Another objective is the development of key process steps. The process sequence and the individual steps must be amenable to automation and low cost manufacturing methods so that the target selling price of $0.70/watt peak (1980$ in 1986) can be achieved. Two process specifications supplied by other contractors have been tested. The Al Silk Screening Process by Spectrolab resulted in cells comparable to those from sputtered Al. The electroless plating of contacts specification supplied by Motorola could be used only with extensive modification. Several experiments suggest that there is some degradation of the front junction during the A1 BSF formation. A SAMICS cost analysis of this process yielded a selling price of $0.75/watt peak in 1980$.

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.