The S-1 machine is part of the Magnetic Fusion Program. The goal of the Magnetic Fusion Program is to develop and demonstrate the practical application of fusion. S-1 is an experimental device which will provide an essential link in the research effort aiming at the realization of fusion power.

The voltammetric characteristics of Pt(II) and Pt(IV) have been examined at a vitreous carbon electrode in slightly acidic 3M (approx. 15 wt %) NaCl solutions. Pt(IV) is reduced to Pt(II) at approx. 0 V and Pt(II) is reduced to Pt(0) at approx. -0.5 V vs Ag-AgCl. The rate of deposition of platinum metal at -0.5 V is very low on bare carbon, but increases as the coverage of platinum increases. The potential at which hydrogen is evolved in this medium is approx. -0.85 V. A technique has been tested for the removal of sub-part-per-million levels of platinum from the high-salinity brine by controlled-potential electrolysis using a reticulated, vitreous-carbon, flow-through electrode. However, at control potentials negative enough to begin to electrodeposit the platinum at a significant rate, simultaneous reduction of hydrogen ion reduces the current and energy efficiency to an unacceptable level.

The electromagnetics of one of several techniques for generating FRCs in a coaxial configuration has been presented. It has been shown that the discussed design satisfies all the electromagnetic requirements for a slow source. The next major issue is the investigation of the plasma physics which will ultimately determine the viability of this concept.

A design for a photovoltaic central power station using tracking concentrators has been developed. The 100 MW plant is assumed to be located adjacent to the Saguaro Power Station of Arizona Public Service. The design assumes an advanced Martin Marietta two-axis tracking fresnel lens concentrator. The concentrators are arrayed in 5 MW subfields, each with its own power conditioning unit. The photovoltaic plant output is connected to the existing 115 kV switchyard. The site specific design allows detailed cost estimates for engineering, site preparation, and installation. Collector and power conditioning costs have been treated parametrically.

An expression to predict the onset of growth of a crack in a quasibrittle material is derived. An energy criterion essentially equivalent to the first two laws of thermodynamics is employed. The criterion is applied to the elastic-plastic crack of Olesiak and Wnuk (1968). 12 references, 3 figures. (ACR)

US Environmental Protection Agency standards for the cleanup and disposal of inactive tailings sites require that control measures for disposal of tailings be designed to be effective for up to 1000 years if reasonably achievable, and, in any case, for 200 years at least. To control the escape of contaminants over such long periods, containment systems must be capable of adjusting to changing environmental conditions. Elements of a containment system include surface covers, biotic barriers, radon barriers, and, in some cases, liners. Each element of the system affects the others, and the whole system responds to the surrounding environment. Interaction is facilitated primarily by soil moisture. Consequently, the control of soil moisture is critical to the effectiveness of containment systems. Protective covers are necessary to prevent disruption of the containment system by physical or biological factors, to provide for the effective functioning of the radon barrier, and to prevent infiltration of excess water that could cause leaching. In order to design protective covers, a working knowledge of the factors and processes impacting tailings piles is required. This report characterizes the major factors and processes, and presents generic solutions based on current research. 65 references, 9 figures, 6 tables.

This is a design document for the Timing and Control Monitor System Upgrade Project. This project is intended to provide a replacement system for the existing user Encoder Monitor Systems and Varian 72 Control Room computer systems. All of these systems reside at the Nevada Test Site. The function of the T and C Monitor System is to gather real-time statistics and data on user defined key variables from control, communication, data acquistion systems, and from the monitoring system itself. The control, communication, and data acquisition systems each operate separately from the monitor system. The T and C Monitor System gathers this data in order to verify the readiness of an event to begin countdown. This includes setup, verification, calibration, and peripheral services, report any failures that may occur during the countdown, verify detonation and containment, and assist reentry activities after the event.

Charged particle exclusive data for high multiplicity U on U events are reported. Analyses are based on comparison with Cugnon's intranuclear cascade model, and the explosion-evaporation simulation of Fai and Randrup. The azimuthal structure of the observed events shows evidence of collective flow. The widely used flow angle methodology proves to be relatively insensitive to collective effects under the conditions of the present experiment. An isotropic pattern of ejectile emission is not reached at maximum multiplicity. 18 refs., 4 figs.

We study the possibility of extending the model used by Moeller and Nix in 1980 to calculate nuclear masses and fission barriers for nuclei throughout the periodic system, to describe compressibility effects and the existence of a neutron skin. 9 references. (WHK)

The decision of whether to cogenerate involves several considerations, including technical, economic, environmental, legal, and regulatory issues. Each of these issues is addressed separately in this handbook. In addition, a chapter is included on preparing a three-phase work statement, which is needed to guide the design of a cogeneration system. In addition, an annotated bibliography and a glossary of terminology are provided. Appendix A provides an energy-use profile of the pulp and paper industry. Appendices B and O provide specific information that will be called out in subsequent chapters.

An inductor-converter bridge (ICB) is a solid state DC-AC-DC power converter system for bidirectional, controllable, energy transfer between two coils. The ICB is suitable for supplying large pulsed power to such magnets as the superconducting equilibrium field coil of the proposed tokamak power reactors from another superconducting energy storage coil.

Pacific Northwest Laboratory (PNL), under contract to the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action Project (UMTRAP) office, has developed an asphalt emulsion cover system to reduce the release of radon from uranium mill tailings. The system has been field tested at Grand Junction, Colorado. Results from laboratory and field tests indicate that this system is effective in reducing radon release to near-background levels (<2.5 pCi m/sup -2/s/sup -1/) and has the properties required for long-term effectiveness and stability. Engineering specifications have been developed, and analysis indicates that asphalt emulsion covers are cost-competitive with other cover systems. This report summarizes the technology for asphalt emulsion radon barrier systems. 59 references, 45 figures, 36 tables.

This report details the performance of Phase II: Verification Tests of the Conspray dynamic sleeve piston coal feeder. The machine performed for 200 hours at 700 psi backpressure, utilizing a 70% to 200 mesh Utah bituminous coal as feedstock. All test work was satisfactorily completed. A post-test inspection was performed. A report of component wear and failures incurred in testing is included as well as suggestions for machine upgrades. The overall conclusion is that the dynamic sleeve piston feeder has proven its ability to operate safely and reliably. When problems have occurred, the machine has demonstrated inherent safety by shutting down without endangering process or personnel. With the recommended improvements incorporated into the feeder, the unit will be ready for installation on a pilot scale coal gasifier. 9 figures, 11 tables.

The post-remedial-action radiological assessment conducted by the ANL Radiological Survey Group in October 1981, following decommissioning and decontamination efforts by Westinghouse personnel, indicated that except for the Advanced Fuels Laboratory exhaust ductwork and north wall, the interior surfaces of the Plutonium Laboratory and associated areas within Building 7 and the Advanced Fuels Laboratory within Building 8 were below both the ANSI Draft Standard N13.12 and NRC Guideline criteria for acceptable surface contamination levels. Hence, with the exceptions noted above, the interior surfaces of those areas within Buildings 7 and 8 that were included in the assessment are suitable for unrestricted use. Air samples collected at the involved areas within Buildings 7 and 8 indicated that the radon, thoron, and progeny concentrations within the air were well below the limits prescribed by the US Surgeon General, the Environmental Protection Agency, and the Department of Energy. The Building 7 drain lines are contaminated with uranium, plutonium, and americium. Radiochemical analysis of water and dirt/sludge samples collected from accessible Low-Bay, High-Bay, Shower Room, and Sodium laboratory drains revealed uranium, plutonium, and americium contaminants. The Building 7 drain lines hence are unsuitable for release for unrestricted use in their present condition. Low levels of …

The objective of this program has been to study the chemistry of the components with high boiling points in a direct coal liquefaction recycle solvent and to identify those components which lead to higher overall yields and improved product stability in the initial coal dissolution step of direct coal liquefaction processes. The major conclusions are: -454 C recycle solvent is primarily aromatic hydrocarbons (73%) and contains almost no asphaltenes; +454 C recycle solvent is primarily asphaltenes and aromatic hydrocarbons; recycle solvent also contains aliphatic hydrocarbons, N-containing aromatics and O-containing aromatics; heteroatoms in coal derived materials seem to be grouped by type, i.e. acidic O and basic N and sulfur occur together; under helium a small net amount of hydrogen and more CO and CO/sub 2/ are produced than under hydrogen; under hydrogen the amounts of H/sub 2/S and hydrocarbon gases are increased and a small amount of hydrogen gas is usually consumed; overall coal conversions to THF solubles are improved by adding more -454 C solvent but decreased by adding +454 C solvent; for added fractions of -454 C solvent the pecent conversion to THF solubles increases in the order aromatic hydrocarbons (+7.2) &gt; aliphatic hydrocarbons (+0.8) &gt; no added …

Liquid metal corrosion can be an important consideration in developing alloys for fusion and fast breeder reactors and other applications. Because of the many different forms of liquid metal corrosion (dissolution, alloying, carbon transfer, etc.), alloy optimization based on corrosion resistance depends on a number of factors such as the application temperatures, the particular liquid metal, and the level and nature of impurities in the liquid and solid metals. The present paper reviews the various forms of corrosion by lithium, lead, and sodium and indicates how such corrosion reactions can influence the alloy development process.

This document presents the results of an effort to transfer existing, but relatively unknown, materials R and D from selected federal laboratories to industry. More specifically, recent materials-related work at seven federal laboratories potentially applicable to improving process energy efficiency and overall productiviy in six energy-intensive manufacturing industries was evaluated, catalogued, and distributed to industry representatives to gauge their reaction. Laboratories surveyed include: Air Force Wright Aeronautical Laboratories Material Laboratory (AFWAL). Pacific Northwest Laboratory (PNL), National Aeronautics and Space Administration Marshall Flight Center (NASA Marshall), Oak Ridge National Laboratory (ORNL), Brookhaven National Laboratory (BNL), Idaho National Engineering Laboratory (INEL), and Jet Propulsion Laboratory (JPL). Industries included in the effort are: aluminum, cement, paper and allied products, petroleum, steel and textiles.

Dry deposition velocities are very difficult to predict accurately. In this article, reported values of dry deposition velocities are summarized. This summary includes values from the literature on field measurements of gas and particle dry deposition velocities, and the uncertainties inherent in extrapolating field results to predict dry deposition velocities are discussed. A new method is described for predicting dry deposition velocity using a least-squares correlation of surface mass transfer resistances evaluated in wind tunnel experiments. 14 references, 4 figures, 1 table.

This report describes the sampling and analytical techniques used for tracer analysis in the Raft River and East Mesa field tests. The collection procedures and sample preservation techniques, analytical methods and possible sources of contamination or error are discussed in detail. 6 refs.

An increased concern about the training of nuclear reactor operators resulted from the incident at TMI-2 in 1979. Purpose of this guide is to provide a general framework for the systematic evaluation of training programs for DOE Category-A reactors. The primary goal of such evaluations is to promote continuing quality improvements in the selection, training and qualification programs.

Following the introduction this report contains the following two sections: (1) field work completed to date; and (2) results and conclusions to date. Field work covers: (1) review of past efforts; (2) well to well tracer testing: (3) injection program; (4) logging program; (5) pressure falloff testing; and (6) injectivity profiles. Results and conclusions cover: (1) injection pressure; (2) temperature at the producers; (3) injectivity profiles; (4) tracer studies; (5) carbon/oxygen logging; (6) well testing; and (7) production data. 12 references, 11 figures, 2 tables.

This volume describes those activities which took place at the Sperry DOE Gravity Head plant site at the East Mesa Geothermal Reservoir near Holtville, California between February 1980, when site preparation was begun, and November 1982, when production well 87-6 was permanently abandoned. Construction activities were terminated in July 1981 following the liner collapse in well 87-6. Large amounts of program time manpower, materials, and funds had been diverted in a nine-month struggle to salvage the production well. Once these efforts proved futile, there was no rationale for continuing with the site work unless and until sufficient funding to duplicate well 87-6 was obtained. Activities reported here include: plant construction and pre-operational calibration and testing, drilling and completion of well 87-6, final repair effort on well 87-6, abandonment of well 87-6, and performance evaluation of well 87.6. (MHR)

A radial transport code for Field-Reversed Configurations (FRCs) is described. Assuming quasi-neutrality and neglecting inertia and viscous force, the evolution of particle densities, temperatures, and magnetic field through a series of equilibrium states is simulated. To solve the equations, transformations of all dependent variables and the one independent variable are carried out. The processes of interest can be decoupled into two distinctive sets of equations that describe adiabatic and nonadiabatic processes. These sets of equations are then solved by two alternating steps adiabatic and nonadiabatic.

The Oak Ridge National Laboratory has been selected as the demonstration site for a new transuranic neutron assay system (NAS) developed at the Los Alamos National Laboratory. In addition, in order to meet specific ORNL program objectives, an upgraded segmented gamma-ray drum scanner has been integrated into the nondestructive assay (NDA) system to serve as a radioisotope identifier and as a quantitative assay backup to the NAS. A verification study, wherein selected waste drums will be emptied into glove boxes and their contents sampled and subsequently gamma-ray assayed, will take place in FY 1984. Results will be compared to those obtained from the NDA techniques. The NAS uses pulsed-neutron interrogation (differential- dieaway technique) and passive neutron measurements to determine fissile component and an upper-limit estimate of the total TRU activity contained in each waste drum. Of the 171 waste drums assayed to date, nine drums were determined to contain less than 10 nCi/g TRU isotopes. An additional number of drums (approximately 20%) are expected to be categorized as non-TRU, which is presently defined as less than 100 nCi/g TRU concentration. This requires a detailed analysis of the data which includes waste matrix compensation, systematic qualitative and quantitative gamma-ray analyses, and …