The studies related to the use of /sup 238/PuO/sub 2/ in radioisotopic power system carried out for the Space and Terrestrial Systems Division of the US Department of Energy by the Los Alamos National Laboratory are reported.

Daily newspaper from Baytown, Texas that includes local, state, and national news along with advertising.

Photograph used for a story in the Daily Oklahoman newspaper. Caption: "Thousands of balloons were released Monday at the dedication of Parker Drilling Co's rig, which has drilling capabilities of 50,000 feet."

One of the fuel concepts being tested and demonstrated as part of the Fuel Performance Improvement Program includes a graphite coating applied to the inner surface of the Zircaloy cladding. The technology for producing acceptable coatings was developed starting with the selection of a suitable graphite and culminating with the coating of 200 cladding tubes for demonstration irradiations in the Big Rock Point Reactor. During the process development, methods for controlling the coating thickness and minimizing its hydrogen content were developed that were compatible with production scale operation. During the same period, the graphite coatings were characterized and their properties were determined, mainly to provide information needed for fuel design and licensing considerations. Purity, structure, coating-to-cladding compatibility, thermal conductivity, and friction/wear characteristics were measured.

Some of the topics addressed are: what the area is like currently in terms of its land use, economics, and demographics; reservoir potentials; how the reservoir might be developed; marketing the final product; financial assistance for development; the legal aspects of development; and barriers to possible development. Some specific topics discussed are: leasing and permitting; heat exchangers for geothermal heating systems; and corrosion, scaling, and materials selection. (MHR)

This report presents the data from five tests of a full-scale trommel processing unsegregated municipal solid waste at throughtputs ranging from 58% to 175% of design capacity, or 32 to 98 Mg/h (36 to 109 tph). The tests were conducted between December 1980 and March 1981 at the Recovery 1 solid waste processing facility in New Orleans, La. Included in the report are a description of the equipment, discussion of the test procedures and primary summaries of data on the trommel mass balance and separation efficiency, and on the analysis of infeed and product samples for size, composition, density, and moisture. Heat content and ash values of the trommel oversize and recovery results on surrogate aluminum cans and flakes also are reported.

The test program for an Active Rotary Flux Compressor (ARFC) has demonstrated conclusively that large compression factors can be obtained with a laminated-iron, wave-wound, rotary flux compressor. Peak-current to startup-current ratios of 17 have been produced with a rotor tip speed of 60 meters per second. Sub-millisecond pulse widths were also measured: the minimum, 590 ..mu..sec (FWHM), was obtained at 5607 rpm with an 8-inch diameter, 4-pole rotor. The machine was operated without a high current output switch, proving the feasibility of a novel commutation scheme described. A computational code has been developed that will calculate the output waveshape of the model ARFC with reasonable accuracy. The code is being refined to better account for saturation in the iron laminations. A second optimization code selects the best design for a given application. This code shows favorable cost effectiveness of large ARFC's over the conventional capacitors to drive flashlamps for large lasers.

Safety Analysis Report DPST-78-124-1 is amended to permit shipment of 6 General Purpose Heat Source (GPHS) capsules (max.). Each capsule contains an average of 2330 curies of /sup 238/Pu, and each pair of capsules is contained in a welded stainless steel primary containment vessel, all of which are doubly contained in a flanged secondary containment vessel. This is in addition to the forms discussed in DPST-78-124-1 and Supplement 1.

Reports and summaries are provided for the following programs: high-level waste process development; alternative waste forms; nuclear waste materials characterization center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; NWVP off-gas analysis; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; verification instrument development; mobility of organic complexes of radionuclide in soils; low-level waste generation reduction handbook; waste management system studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology program; high-level waste form preparation; development of backfill materials; development of structural engineered barriers; disposal charge analysis; analysis of spent fuel policy implementation; spent fuel and pool component integrity program; analysis of postulated criticality events in a storage array of spent LWR fuel; asphalt emulsion sealing of uranium mill tailings; liner evaluation for uranium mill tailings; multilayer barriers for sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; and revegetation of inactive uranium tailings sites.

The conclusions of each of three previous non-US incentives volumes and the conclusions of the comparisons volume which looks at incentives in four countries including the United States are summarized. Summaries of the patterns of incentive actions in France, West Germany, and Japan are presented first, followed by a summary of the four-country comparisons volume itself. Suggestions for solar policy which are based on the comparison of incentive actions in the four countries are presented. The definitions and methods used in each of the single-country studies are explained in detail in those volumes. A brief explanation of the procedures is offered. Each volume was divided into three parts: a survey of current thought about incentives for solar energy production; a view of the energy incentive landscape for one particular year; and an analysis of the major energy forms (nuclear, hydro, coal, electricity, oil, and gas) along the path from exploration to waste management, including the costs of incentives at each step in constant national currency. Following the theoretical approach developed for studying US energy incentives, the researchers in each country classified incentives into the following six categories: taxation, disbursements, requirements traditional services, nontraditional services, and market activities.

Nineteen papers are included. A separate abstract was prepared for each one. Summaries of workshop discussions on types of incentives are also included. (MHR)

Volume 1 provides a Program Overview, presenting highlights of the technical accomplishments of the elements of the Program, a summary of activities carried out under the Glass Laser Experiments Lead Laboratory Program, as well as discussions of Program resources and facilities. Section 2, also in the first volume, covers the work on solid state Nd:glass lasers, including systems operations, Nova and Novette system development, and supporting research and development activities.

Volume 3 is comprised of three sections, beginning with Section 8 on Advanced Lasers. Both theoretical and experimental research and development activities on advanced laser systems are presented here. Section 9 contains the results of studies in areas of energy and military applications, including those relating to electrical energy production by inertial confinement fusion systems. Finally, Section 10 presents results from selected activities in the Advanced Isotope Separation Program.

Neutronics calculations by Engholm show that without additional shielding even the first fusion test reactors such as the Fusion Engineering Device will produce lifetime doses at magnet insulator locations that exceed the radiation tolerance of glass-fabric-filled (gff) epoxies now used. To explore the possible use of an alternative insulator, the mechanical strength of pure and recently available gff polyimides was studied as a function of gamma-ray irradiation at 4.9 K to 100 MGy (10/sup 10/ rads). After a postirradiation anneal at 307/sup 0/K the flexure and compressive strengths of the gff materials measured at 77/sup 0/K were reduced by up to 40% for 100 MGy while the pure material changed little. Testing done at 300/sup 0/K gave similar results, but all stress values were about 40% less. Compared to earlier epoxy studies we find that, overall, the gff polyimides are 5 to 10 times more radiation resistant than comparably prepared gff epoxies.

It is shown that the negative real part of an input impedance does not mean instability of the related circuit. A negative real part of the input impedance means only that the concerned circuit is active.

Unexpected phase structure in four dimensional lattice gauge theory based on the groups SO(3) and SU(5) have prompted studies of variations on the Wilson action for SU(2). A rich phase structure related to the decomposition of SU(2) into SO(3) and Z/sub 2/ is found. The scale of asymptotic freedom has a dramatic dependence on the choice of lattice action.

To insure adequate supplies of plutonium and tritium for defense purposes, an independent evaluation was made by Los Alamos National Laboratory of the numerous alternatives to the proposed replacement production reactors (RPR). This effort concentrated on the defense fuel cycle operation and its technical implications in identifying the principal alternatives for the 1990s. The primary options were identified as (1) existing commercial reactors, (2) existing and planned government-owned facilities (not now used for defense materials production), and (3) other RPRs (not yet proposed) such as CANDU or CANDU-type heavy-water reactors (HWR) for both plutonium and tritium production. The evaluation considered features and differences of various options that could influence choice of RPR alternatives. Barring a change in the US approach to civilian and defense fuel cycles and precluding existing commercial reactors at government-owned sites, the most significant alternatives were identified as a CANDU-type HWR at Savannah River Plant (SRP) site or the Three Mile Island commercial reactor with reprocessing capability at Barnwell Nuclear Fuel Plant and at SRP.

The purpose of the Workshop on Compositional and Microstructural Analysis of Nuclear Waste Materials, conducted November 11 and 12, 1980, was to critically examine and evaluate the various methods currently used to study non-radioactive, simulated, nuclear waste-form performance. Workshop participants recognized that most of the Materials Characterization Center (MCC) test data for inclusion in the Nuclear Waste Materials Handbook will result from application of appropriate analytical procedures to waste-package materials or to the products of performance tests. Therefore, the analytical methods must be reliable and of known accuracy and precision, and results must be directly comparable with those from other laboratories and from other nuclear waste materials. The 41 participants representing 18 laboratories in the United States and Canada were organized into three working groups: Analysis of Liquids and Solutions, Quantitative Analysis of Solids, and Phase and Microstructure Analysis. Each group identified the analytical methods favored by their respective laboratories, discussed areas needing attention, listed standards and reference materials currently used, and recommended means of verifying interlaboratory comparability of data. The major conclusions from this workshop are presented.

The approximate stoichiometry of liquefaction, from data of two PDU runs and a laboratory run is Wood (100 g) + CO (0.1 - 0.4 Mol) ..-->.. CO/sub 2/ (0.5 - 1.0 Mol) + H/sub 2/O (0.4 - 0.8 Mol) + Product (55 - 64 g). Product includes wood oil, water soluble organics and residues. Water is formed by decomposition, carbon dioxide by decomposition and reduction of wood oxygen by CO. Aqueous products include many carboxylic acids plus a roughly equal percentage of non-acids. The wood oil is divided into a neutral fraction and three phenolic fractions of varying molecular weight. Some specific compounds found in water and oil phases are listed.

The survey purpose, methods, and statistical methods are presented. Results are discussed according to: area differences in background variables, area differences in health variables, area differences in annoyance reactions, and comparison of symptom frequencies with age, smoking, and drinking. Included in appendices are tables of data, enumeration forms, the questionnaire, interviewer cards, and interviewer instructions. (MHR)

An airborne predawn radiometric temperature survey was flown over the Long Valley KGRA. Radiometric temperatures were recorded at 10 to 12 ..mu..m and 4.5 to 5.5 ..mu..m. They were corrected to obtain true land-surface temperatures in agreement with field data. After accounting for thermal effects from surface features, there remained a thermal anomaly. The anomalous zone encompassed 2 km/sup 2/. It was a dry land area with a predawn surface temperature which averaged 1.4 +- 0.3/sup 0/C warmer than ambient. This area coincided with a thermal discharge zone where deep temperature gradients were 5 to 30 times normal. The predawn radiometric survey clarified and supplemented conclusions drawn from 6 to 30m deep field surveys. Heat from hydrothermal discharge was stored in a shallow aquifer and conducted to the surface.

A significant part of evaluating a geologic formation as a nuclear waste repository involves the modeling of contaminant transport in the surrounding media in the event the repository is breached. The commonly used contaminant transport models are deterministic. However, the spatial variability of hydrologic field parameters introduces uncertainties into contaminant transport predictions. This paper discusses the application of geostatistical techniques to the modeling of spatially varying hydrologic field parameters required as input to contaminant transport analyses. Kriging estimation techniques were applied to Hanford Reservation field data to calculate hydraulic conductivity and the ground-water potential gradients. These quantities were statistically combined to estimate the groundwater pore velocity and to characterize the pore velocity estimation error. Combining geostatistical modeling techniques with product error propagation techniques results in an effective stochastic characterization of groundwater pore velocity, a hydrologic parameter required for contaminant transport analyses.

Project activities and publications are listed. (MHR)

When angular momentum is added to a nucleus, it is, of course, carried by the individual nucleons, but two limiting types of behavior may be distinguished: (1) a small number of high-j particles align with the rotation axis and (2) the nucleus is deformed and rotates as a whole. At high spin all nuclei seem to show a compromise utilizing both motions. The excited nuclei left as products of (HI,xn) reactions have so many pathways down that none of the ..gamma..-ray transitions have enough intensity to be seen individually until the population gathers near the yrast line. This occurs usually between spin 20 to 40 h-bar. All our information on the higher states comes from their continuum spectra. With the new techniques that are developing, including the use of multiplicity filters, total-energy spectrometers, energy correlation studies, crystal balls, and observation of giant dipole resonances in the continuum spectra, there is hope to learn much about the nature of the high-spin states.