A numerical study is made of a problem dealing with calculation of the magnetic field B vector, the magnetic vector potential A vector, and first partial derivatives of the B vector field and A vector components for two kinds of magnetic sources: (1) current-carrying straight wire of finite length; and (2) current-carrying closed polygon. No restrictions are imposed on the type of the polygon and hence it need not be plane and can consist of arbitrary number of straight wires of arbitrary lengths. Separate consideration of the polygon case makes the numerical procedure more efficient than that based on the linear superposition of the straight-wire sources. All necessary quantities are derived analytically in simple and closed forms without use of any approximations and exact relations are utilized to the greatest possible extent to give an efficient algorithm. Thus, the involved numerical procedures are quite simple, fast, accurate, and straightforward. Results are given in four different coordinate systems (cartesian, cylindrical, spherical, and local toroidal) and results in any other orthogonal coordinates can be obtained with only a few minor modifications.

Present and future irradiation facilities for the study of fusion reactor irradiation damage are reviewed. Present studies are centered on irradiation in accelerator-based neutron sources, fast- and mixed-spectrum fission reactors, and ion accelerators. The accelerator-based neutron sources are used to demonstrate damage equivalence between high-energy neutrons and fission reactor neutrons. Once equivalence is demonstrated, the large volume of test space available in fission reactors can be used to study displacement damage, and in some instances, the effects of high-helium concentrations and the interaction of displacement damage and helium on properties. Ion bombardment can be used to study the mechanisms of damage evolution and the interaction of displacement damage and helium. These techniques are reviewed, and typical results obtained from such studies are examined. Finally, future techniques and facilities for developing damage levels that more closely approach those expected in an operating fusion reactor are discussed.

We have demonstrated experimentally that thorium oxide may be used as a catalyst with CO + H/sub 2/ mixtures to produce either methanol or a mixture of hydrocarbons from C/sub 1/ to C/sub 5/ (saturated and unsaturated). The immunity of ThO/sub 2/ to poisoning by sulfur compounds makes its use very attractive for industrial applications. We are proposing to optimize the experimental conditions of the catalytic process using a one-inch reactor and to scope and define the experimental conditions for a pilot plant demonstration.

The nonlinear nonresonant interaction of plasma waves and particles is formulated in a Hamiltonian kinetic theory which treats the wave-action and particle distributions on an equal footing, thereby displaying reciprocity relations. In the quasistatic limit, a nonlinear wave-kinetic equation is obtained. The generality of the formalism allows for applications to arbitrary geometry, with the nonlinear effects expressed in terms of the linear susceptibility.

Neutron cross-section libraries in the AMPX master interface format have been created for three reactor types. Included are an 84-group library for use with light-water reactors, a 27-group library for use with heavy-water CANDU reactors and a 126-group library for use with liquid metal fast breeder reactors. In general, ENDF/B data were used in the creation of these libraries, and the nuclides included in each library should be sufficient for most neutronic analyses of reactors of that type. Each library has been used successfully in fuel depletion calculations.

Information is presented concerning engineering, personnel, reactor operators, health physics personnel, competing demands on technical manpower, personnel management issues, and emerging technology.

A preliminary analysis was made of the initial startup data taken between October 20 and November 2, 1981 for the 5 MW(e) Pilot Geothermal Power Plant located at the Raft River Site in southeast Idaho. This plant utilizes a dual-boiling isobutane binary cycle. Two test conditions were selected for analysis: (1) a thermal loop test with 94% of the design geofluid flow, and (2) a test at about three-fourths of the design geofluid flow in which one megawatt was generated from working-fluid flow through the low-pressure stage of the turbine. Component and system energy balances were made, and comparisons between experimental results and computer simulations of the plant were conducted. A preliminary analysis of condenser tube wall temperatures was performed. Except for a malfunction in the high pressure turbine throttle valve system, the plant performed generally as predicted, and the testing was judged to be successful.

This report documents the operating experience with two aluminum blades used on the DOE/NASA Mod-0A 200-kilowatt wind turbine located at Clayton, New Mexico. Each Mod-0A aluminum blade is 59.9 feet long and weighs 2360 pounds. The aluminum Mod-0A blade design requirements, the selected design, fabrication procedures, and the blade analyses are discussed. A detailed chronology is presented on the operating experience of the Mod-0A aluminum blades used at Clayton, New Mexico. Blade structural damage was experienced. Inspection and damage assessment were required. Structural modifications that were incorporated to the blades successfully extended the useful operating life of the blades. The aluminum blades completed the planned 2 years of operation of the Clayton wind turbine. The blades were removed from service in August 1980 to allow testing of advanced technology wood composite blades.

This document illustrates how an Environmental, Safety and Health (ES and H) Assurance Program may be implemented. The generic definition of ES and H Assurance Programs is given in a companion document entitled An Environmental, Safety and Health Assurance Program Standard. This document is concerned with the performance of reviews - a technique useful for both control and assurance aspects of ES and H Assurance Programs. Emphasis is given to reviews conducted at the operational level of an institution.

Nitrate salts have been used for years as a high-temperature heat transfer medium in the chemical and metal industries. This experience is often cited as an argument for the use of these salts in large-scale solar energy systems. However, this industrial experience has not been well documented and a study was carried out to provide such information to the solar community and to determine the applicability of this data base. Seven different industrial plants were visited and the plant operators were interviewed with regard to operating history and experience. In all cases the molten salt systems operate without problems. However, it is not possible to apply the base of industrial experience directly to solar thermal energy applications because of differences in operating temperature, salt composition, alloys used, and thermal/mechanical conditions.

An electronic interface between a Digital Equipment Corporation (DEC) LSI-11 microcomputer and a LeCroy Research Systems model 3001 qVt multichannel analyzer is described in detail. This interface provides for 16-bit parallel data transfer from the memory of the analyzer to the memory of the computer. An unusual feature of the interface is a provision that allows storage of counts of logic pulses (e.g., from radiation detector discriminators) in the first 16 channels of the analyzer's memory. A further provision allows use of a LeCroy printer and display interface that is designed specifically as a companion module to the qVt analyzer.

We have investigated the compatibility of the Zr-Al alloy bulk getter with a tokamak plasma environment, where the hydrogenic fluxes are sufficient to cause embrittlement in relatively short times. Under normal operating conditions with the getters activated, it is necessary to regenerate the absorbed hydrogenic species before the embrittlement limit is reached. We present a method for determining the loading under tokamak conditions where the Zr-Al surface characteristics can change. During glow discharge cleaning and pulse discharge cleaning, it is not convenient to regenerate. We find, however, that during the cleaning operations the getter self-inerts, thus limiting the loading. We present data and a model which accounts for this behavior in terms of impurity adsorption on the room temperature getter surface during the cleaning operations.

A research program is under way to systematically characterize the type of radwastes which may be generated in cleanup procedures following off-normal reactor operations. Specifically, the program is presently investigating how the properties of wastes containing ion-exchange media may be modified by heavy doses of irradiation from sorbed radionuclides. Special effort is being devoted toward quantifying the effects of factors such as radiation dose rate, chemical loading on the ion exchangers, moisture content and composition of external media, etc., which may inflence the relation between laboratory test results and field performance. Initial irradation damage measurements have been carried out on organic cation resin IRN-77 in both hydrogen and sodium forms. Gamma irradiation of both of these materials produces water soluble acidic decomposition products; the acid product yields depend on the chemical loading and are lower for the sodium form.

This report describes a subprogram, SPLP(), for solving linear programming problems. The package of subprogram units comprising SPLP() is written in Fortran 77. The subprogram SPLP() is intended for problems involving at most a few thousand constraints and variables. The subprograms are written to take advantage of sparsity in the constraint matrix. A very general problem statement is accepted by SPLP(). It allows upper, lower, or no bounds on the variables. Both the primal and dual solutions are returned as output parameters. The package has many optional features. Among them is the ability to save partial results and then use them to continue the computation at a later time.

After a discussion of solar greenhouse phenomena and the potential for heat collection and food production, design recommendations are provided for attached heat collecting solar sunspaces and for attached food producing solar greenhouses. Also, design of a single solar structure to maximize heat collection and food production is considered. A method of predicting the performance for attached heat collecting solar sunspaces is given in which the solar savings fraction is calculated. (LEW)

Coated particle waste forms have been developed as part of the multibarrier concept at Pacific Northwest Laboratory under the Alternative Waste Forms Program for the Department of Energy. Primary efforts were to coat simulated nuclear waste glass marbles and ceramic pellets with low-temperature pyrolytic carbon (LT-PyC) coatings via the process of chemical vapor deposition (CVD). Fluidized bed (FB) coaters, screw agitated coaters (SAC), and rotating tube coaters were used. Coating temperatures were reduced by using catalysts and plasma activation. In general, the LT-PyC coatings did not provide the expected high leach resistance as previously measured for carbon alone. The coatings were friable and often spalled off the substrate. A totally different concept, thermal spray coating, was investigated at PNL as an alternative to CVD coating. Flame spray, wire gun, and plasma gun systems were evaluated using glass, ceramic, and metallic coating materials. Metal plasma spray coatings (Al, Sn, Zn, Pb) provided a two to three orders-of-magnitude increase in chemical durability. Because the aluminum coatings were porous, the superior leach resistance must be due to either a chemical interaction or to a pH buffer effect. Because they are complex, coated waste form processes rank low in process feasibility. Of all the …

The economic feasibility is assessed of utilizing solar energy to augment an existing fossil fuel system to generate industrial process heat. Several case studies in the textile and food processing industries in the southern United States were analyzed. Sensitivity analyses were performed, and comparisons illustrating the effects of the Economic Recovery Tax Act of 1981 were made. The economic desirability of the proposed solar systems varied with the type of system selected, location of the facility, state tax credits, and type of fuel displaced. For those systems presently not economical, the projected time to economic feasibility was ascertained.

The purpose of this research was to collect, analyze, and summarize all of the nuclear power-related surveys conducted in the United States through June 1981, that we could obtain. The surveys collected were national, statewide, and areawide in scope. Slightly over 100 surveys were collected for an earlier, similar effort carried out in 1977. About 130 new surveys were added to the earlier survey data. Thus, about 230 surveys were screened for inclusion in this report. Because of space limitations, national surveys were used most frequently in this report, followed distantly by state surveys. In drawing our conclusions about public beliefs and attitudes toward nuclear power, we placed most of our confidence in survey questions that were used by national polling firms at several points in time. A summary of the research findings is presented, beginning with general attitudes toward nuclear power, followed by a summary of beliefs and attitudes about nuclear power issues, and ended by a summary of beliefs and attitudes regarding more general energy issues.

On October 5, 1979, the Lithium Processing Test Loop (LPTL) developed a lithium leak in the electromagnetic (EM) pump channel, which damaged the pump, its surrounding support structure, and the underlying floor pan. A thorough analysis of the causes and consequences of the pump failure was conducted by personnel from CEN and several other ANL divisions. Metallurgical analyses of the elliptical pump channel and adjacent piping revealed that there was a significant buildup of iron-rich crystallites and other solid material in the region of the current-carrying bus bars (region of high magnetic field), which may have resulted in a flow restriction that contributed to the deterioration of the channel walls. The location of the failure was in a region of high residual stress (due to cold work produced during channel fabrication); this failure is typical of other cold work/stress-related failures encountered in components operated in forced-circulation lithium loops. Another important result was the isolation of crystals of a compound characterized as Li/sub x/CrN/sub y/. Compounds of this type are believed to be responsible for much of the Fe, Cr, and Ni mass transfer encountered in lithium loops constructed of stainless steel. The importance of nitrogen in the mass-transfer mechanism has …

The potential geothermal direct-use energy market and its application to projects in California are assessed. Project identification effort is to be focused on those that have the highest probability for near-term successful commercial operations. Near-term herein means 2 to 5 years for project implementation. Phase I has been focused on defining and assessing: (1) the geothermal direct-use resources that are suitable for near-term utilization; and (2) the generic applications (municipal heating districts, horticultural greenhouse firms, laundries, etc.) that are suitable for near-term projects. Five economic development regions in the state, containing recognized geothermal direct-use resources, have been defined. Thirty-eight direct use resources have been evaluated in these regions. After assessment against pre-selected criteria, twenty-seven have been rated with a priority of I, II or III, thereby qualifying them for further marketing effort. The five areas with a priority of I are summarized. These areas have no perceived impediments to near-term development. Twenty-nine generic categories of applications were assessed against previously selected criteria to determine their near term potential for direct use of geothermal fluids. Some twenty industry, commercial and institutional application categories were rated with a priority of I, II or III and warrant further marketing efforts. The seven categories …

The Savannah River Laboratory is conducting tests to determine the best operating conditions of pumps used to transfer insoluble radioactive sludges from old to new waste tanks. Because it is not feasible to conduct these tests with real or chemically simulated sludges, kaolin clay is being used as a stand-in for the solid waste. The rheology tests described herein were conducted to determine whether the properties of kaolin were sufficiently similar to those of real sludge to permit meaningful pump tests. The rheology study showed that kaolin can be substituted for real waste to accurately determine pump performance. Once adequately sheared, kaolin properties were found to remain constant. Test results determined that kaolin should not be allowed to settle more than two weeks between pump tests. Water or supernate from the waste tanks can be used to dilute sludge on an equal volume basis because they identically affect the rheological properties of sludge. It was further found that the fluid properties of kaolin and waste are insensitive to temperature.

Potential cumulative impacts on the transportation system are assessed and recommendations are made as to options for handling future transportation development. The area is served by state highways, county roads, and an internal network of private roads. Access into the area is limited, and the roads must handle a variety of traffic including an unusually high percentage of heavy trucks transporting construction equipment and materials, hazardous chemicals, and toxic wastes. In conducting the transportation study public documents on geothermal power plant developments were researched and field trips to inspect the transportation facilities were made. People who have a special interest in the transportation system were also interviewed. In addition, traffic, accident, and road data were analyzed. Traffic forecasts based on projected geothermal resource develpoment were made. All access roads are of substandard design and efficient in structural adequacy. With projected traffic at 40% above the current level for most of the next six years, it is expected that cumulative impacts will cause accelerated degradation of the existing roads.

A review of the various solidification agents and techniques that are currently available or potentially applicable for the solidification of low-level radioactive wastes is presented. An overview of the types and quantities of low-level wastes produced is presented. Descriptions of waste form matrix materials, the wastes types for which they have been or may be applied and available information concerning relevant waste form properties and characteristics follow. Also included are descriptions of the processing techniques themselves with an emphasis on those operating parameters which impact upon waste form properties. The solidification agents considered in this survey include: hydraulic cements, thermoplastic materials, thermosetting polymers, glasses, synthetic minerals and composite materials. This survey is part of a program supported by the United States Department of Energy's Low-Level Waste Management Program (LLWMP). This work provides input into LLWMP efforts to develop and compile information relevant to the treatment and processing of low-level wastes and their disposal by shallow land burial.

A real-time method for testing the validity of linear models of nonlinear processes is described and evaluated. Using generalized likelihood ratios, the model dynamics are continually monitored to see if the process has moved far enough away from the nominal linear model operating point to justify generation of a new linear model. The method is demonstrated using a seventh-order model of a natural circulation steam generator.