The dispersion of a quantal oscillator with a time-dependent inertial mass is considered. For a special class of time dependence, an empirical method is formulated for predicting the asymptotic behavior of such a system. This method is then applied to the prediction of charge widths in strongly damped nuclear collisions and in fission.

The following ADIP tasks are reported on: MFE-5 in-reactor fatigue crack growth in 316 SS in ORR, titanium alloy tensile properties after neutron irradiation in EBR-II, voids in neutron-irradiated Ti alloys, fabrication of ferritic alloys for RB-1 experiment in HFIR, microstructural examination of commercial ferritic alloys irradiated to very high fluence, microstructural examination of HT-9 archive material from the AD-2 test, and swelling of commercial alloys irradiated to a very high fluence. (DLC)

Adsorption of iso-pentanol, pentanoic acid, and benzyl alcohol at the mercury-solution interface was studied in HC1O/sub 4/, H/sub 2/SO/sub 4/, NaNO/sub 3/, and NaF electrolytes. The Frumkin isotherm equation Ba = (theta/(1-theta))exp(2..cap alpha..theta) together with the implied charge vs. surface excess relation: q = (1-theta)q/sub w/ + thetaQ were used to analyze the experimental data. Linear charge vs surface excess plots were obtained for the aliphatic compounds over the entire potential region studied; for benzyl alcohol, plots were linear only at anodic potentials. The slopes of these lines agreed with those predicted by the above equation, with Q = C/sub org/(V-V/sub n/), for cathodic potentials. At potentials anodic to the electrocapillary maximum, deviations between experimental and theoretical slopes appeared. In the model proposed, the double layer consists of two parts. The layer closest to the surface is restricted to water molecules and specifically adsorbed ions. The second layer contains organic molecules exclusively; any charge necessary to balance the surface charge is considered to be in a monolayer adjacent to the organic layer. From the slope of the charge vs surface excess plots, it is possible to calculate the charge on the covered portion of the surface and then calculate the …

An advanced absorber assembly design has been developed for breeder reactor control rod applications that provides for improved in-reactor performance, longer lifetimes, and reduced fabrication costs. The design comprises 19 vented pins arranged in a circular array inside of round duct tubes. The absorber material is boron carbide; cladding and duct components are constructed from the modified Type 316 stainless steel alloy. Analyses indicate that this design will scram 30 to 40% faster than the reference FFTF absorber assembly. The basic design characteristics of this advanced FFTF absorber assembly are applicable to large core breeder reactor design concepts.

A prototype voice verification system has been installed which provides the required positive identification at the main site access control point. This system compares an individual's file voice print with a sample voice print obtained from the individual when an attempt is made to enter the site. The voice system transmits the individual's identity to a central processor. The central processor associates that individual's authorization file with a card-key obtained at the access point. The system generates a record of personnel movement, provides a personnel inventory on a real-time basis, and it can retrieve a record of all prior events. The system installed at the Barnwell Nuclear Fuel Plant is described.

Task 2 involved the establishment of an engineering and economic model for the evaluation of various options in water electrolysis. The mode, verification of the specific coding and four case studies are described. The model was tested by evaluation of a nearly commercial technology, i.e., an 80-kW alkaline electrolyte system, operating at 60/sup 0/C, which delivers approximately 255 SLM, hydrogen for applications such as electrical generation cooling or semiconductor manufacturing. The calculated cost of hydrogen from this installed non-optimized case system with an initial cost to the customer of $87,000 was $6.99/Kg H/sub 2/ ($1.67/100 SCF) on a 20-yr levelized basis using 2.5 cents/kWh power costs. This compares favorably to a levelized average merchant hydrogen cost value of $9.11/Kg H/sub 2/ ($2.17/100 SCF) calculated using the same program.

The objectives of this project are twofold: (1) to investigate new amorphous semiconductor (a-SC) materials, in which recombination centers are passivated, using plasma deposition techniques; and (2) to characterize the optoelectronic properties pertaining to both majority-carrier and minority-carrier transport in as-deposited films and in devices. The electronic properties of plasma-deposited a-Si:H alloys were studied as functions of oxygen and nitrogen impurities. Over a wide range of processing conditions, features displayed by the data include: (1) anomalous behavior in photoconductivity versus temperature for films deficient in either, or both, impurities (peaks appear that are associated with thermal-quenching processes and supralinearity); and (2) modification to classic behavior in photoconductivity owing to synergistic effects of oxygen and nitrogen. Correlations with photoluminescence were observed. Within the context of an emerging spectroscopy, optical emission spectroscopy was found to be a useful technique for the detection of emitting reactive species in the plasma. The presence of impurities, such as N/sub 2/ and chlorosilanes, was diagnosed.

The primary objectives of this project are twofold: (i) to investigate new amorphous semiconductor (a-Sc) materials, in which recombination centers are passivated, using plasma deposition techniques; and (ii) to characterize the optoelectronic properties pertaining to both majority-carrier and minority-carrier transport in as-deposited films and in devices. The specific goals in FY 1980 are: (i) to continue investigations of the effects of atmospheric impurities, i.e., nitrogen and oxygen, on the optoelectronic properties of a-Si:H alloys; and (ii) to initiate a study of the effects of these impurities upon the photovoltaic conversion efficiencies of diagnostic devices that are fabricated using such alloys. The following activities were emphasized in the program: (i) an expansion of plasma studies using optical emission spectroscopy in order to identify emitting reactive species due to impurities; and (ii) electrical and optical measurements on alloys with calibrated impurity levels by measurments of photoconductivity, photoluminescence, vibrational spectroscopy, etc.; and (iii) completing the apparatus for device measurements of spectral response, dark I-V characteristics, illuminated I-V characteristics, etc. Associated with the last activity, the fabrication of solar cells was begun using low-impurity a-Si:H materials and various a-Si:(H,O,N) alloys. Progress is reported. (WHK)

Many of the processing steps in the nuclear fuel cycle generate aqueous effluent streams bearing contaminants that can, because of their chemical or radiological properties, pose an environmental hazard. Concentration of such contaminants must be reduced to acceptable levels before the streams can be discharged to the environment. Two classes of contaminants, nitrates and heavy metals, are addressed in this study. Specific techniques aimed at the removal of nitrates and radioactive heavy metals by biological processes are being developed, tested, and demonstrated. Although cost comparisons between biological processes and current treatment methods will be presented, these comparisons may be misleading because biological processes yield environmentally better end results which are difficult to price. The fluidized-bed biological denitrification process is an environmentally acceptable and economically sound method for the disposal of nonreusable sources of nitrate effluents. A very high denitrification rate can be obtained in a FBR as the result of a high concentration of denitrification bacteria in the bioreactor and the stagewise operation resulting from plug flow in the reactor. The overall denitrification rate in an FBR ranges from 20- to 100-fold greater than that observed for an STR bioreactor. It has been shown that the system can be operated …

The operation, maintenance and modifications to the Westinghouse gasification process development unit during the quarter are reviewed. The tests of the gasifier-agglomerator included direct coal feed as well as oxygen-blown gasification of a char or coal bed. Then the whole system was tested in single and double stage operation. Laboratory support involved fluidized bed test facilities at ambient temperature and at design temperature for devolatilization and gasification studies. Other laboratory systems were related to thermal analysis and pressurized high temperature studies of gasification and gas cleaning. (LTN)

A detailed description of the SERI Advanced Component Research Facility (ACRES) is given. Background information explicates the facility's history, developed around the two Omnium-G parabolic dish concentrators. The Omnium-G concentrators and electrical power plant are described. The purpose and a detailed descripttion of ACRES is also given. Included is a description of the measurement capabilities, the controls, and each component of the facility.

The overall objective of this program is to define an advanced converter system employing 1980's technology in all subsystem and component areas for use in electrochemical energy storage systems. Additional experimental effort will validate elements of the advanced commutation circuitry on a full-scale breadboard basis. Improved models of battery electrical characteristics are being defined and experimental apparatus is being designed to measure these characteristics and to enable better definition of the battery-power conditioner interface. Improvement of energy-storage system performance through modification of battery converter characteristics will also be investigated. During this first year of the contract, a new more advanced concept for power conditioning based on a concept defined by United Technologies Corporation for fuel cell use was evaluated. This high switching frequency concept has the potential for significantly reducing the size and cost of battery plant power conditioners. As a result, the Department of Energy authorized redirection of the program to first evaluate this new concept and then to reorient the program to adopt this concept as the primary one. Progress is reported. (WHK)

The subject of this paper is a wavy electrode precipitator which employs a new collecting electrode. The wavy electrode precipitator incorporates a contoured collecting electrode geometry which produces a nearly uniform electric field along the electrode. This feature allows operation with higher average electric field strengths near the electrode than in conventional designs. The wavy electrode provides separated flow zones within its valleys, which fluid dynamically shield particles from the main stream. The design also provides mechanical rigidity to vertical bending without the sharp flanges normal to the flow commonly found in conventional precipitators. These features permit increased performance for all particle sizes, but especially help in the precipitation of fine particles which are normally the most difficult to collect.

This report contains descriptions of the activities of all the projects supported by the Advanced Fusion Concepts Branch of the Office of Fusion Energy, US Department of Energy. These descriptions are project summaries of each of the individual projects, and contain the following: title, principle investigators, funding levels, purpose, approach, progress, plans, milestones, graduate students, graduates, other professional staff, and recent publications. Information is given for each of the following programs: (1) reverse-field pinch, (2) compact toroid, (3) alternate fuel/multipoles, (4) stellarator/torsatron, (5) linear magnetic fusion, (6) liners, and (7) Tormac. (MOW)

The results are presented of work performed on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Work covered in this report includes the activities associated with the status of the simulated reactor helium supply system, testing equipment, and gas chemistry analysis instrumentation and equipment. The status of the data management system is presented. In addition, the progress in the screening test program is described.

Objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Work covered in this report includes the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described; this includes: screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850 and 950/sup 0/C. The initiation of air creep-rupture testing in the intensive screening test program is discussed. In addition, the status of the data management system is described.

Results are presented of work performed on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Included are the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described, including screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850, and 950/sup 0/C.

The results of work performed from July 1, 1979 through September 30, 1979 on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program are presented. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Work covered in this report includes the activities associated with the status of the simulated reactor helium supply system, testing equipment, and gas chemistry analysis instrumentation and equipment. The status of the data management system is presented. In addition, the progress in the screening test program is described.

Objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Work covered in this report includes the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described: screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850, 950 and 1050/sup 0/C. Initiation of controlled purity helium creep-rupture testing in the intensive screening test program is discussed. In addition, the results of 1000-hour exposures at 750 and 850/sup 0/C on several experimental alloys are discussed.

This report presents the results of work performed from October 1, 1979 through December 31, 1979. Work covered in this report includes the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described. This includes: screening creep results, weight gain and post-exposure mechanical properties for materials thermally exposed at 750/sup 0/ and 850/sup 0/C (1382/sup 0/ and 1562/sup 0/F). In addition, the status of the data management system is described.

Considering the high temperature, low O/sub 2/, high C environment of operation in the Very High Temperature Reactor (VHTR) Systems, the utilization of coatings is envisaged to hold potential for extending component lifetimes through the formation of stable and continuous oxide films with enhanced resistance to C diffusion. A survey of the current state of technology for high temperature coatings has been performed. The usefulness of these coatings on the Mo, Ni, and Fe base alloys is discussed. Specifically, no coating substitute was identified for TZM other than the well known W-3 (pack silicide) and Al/sub 2/O/sub 3/ forming coatings were recommended for the Fe and Ni base structural materials. Recommendations as to coating types and processng have been made based on the predicted VHTR component size, shape, base metal and operational environment. Four tests designed to evaluate the effects of selected combinations of coatings and substrate matrices are recommended for consideration.

The BNL design of a high energy neutral beam injector is based on the neutralization of negative ions, a process that remains very efficient even at energies up to and above 1 MeV. The principal elements of such an injector are: source of negative ions, beam extraction and transport system, accelerator, neutralizing cell, and system for the removal and dumping (or energy recovery) of the remaining charged components of the beam. Among several possible source geometries, the most advanced is the BNL version of the magnetron. Best results have been obtained by using geometrical focusing of surface produced H/sup -/ ions and an asymmetric discharge chamber. A large water cooled model is being fabricated, to deliver 1-2 A of H/sup -//D/sup -/ beam currents in pulses longer than 5 s, with a source power efficiency of about 6 kW/A and a gas efficiency of 6-10%. First tests are scheduled for July 1980. Two options of the beam transport are being studied theoretically and experimentally: a weak focusing bending magnet and a strong focusing chain of electrostatic quadrupoles.

The development and initial performance testing of an advanced integrated safeguards system at the Barnwell Nuclear Fuel Plant (BNFP) is described. The program concentrates on the integration and coordination of physical security and nuclear materials control and accounting at a single location. Hardware and software for this phase have been installed and are currently being evaluated. The AGNS/DOE program is now in its third year of development at the BNFP.

A process is described for making waste glass that circumvents the problems of dissolving nuclear waste in molten glass at high temperatures. Because the reactive mixing process is independent of the inherent viscosity of the melt, any glass composition can be prepared with equal facility. Separation of the mixing and melting operations permits novel glass fabrication methods to be employed.