The {sup 252}Cf-source-driven noise analysis method has been used in measurements for subcritical configurations of fissile systems for a variety of applications including a dynamic measurement that was the first step in applying this method to monitor fuel in a future reprocessing plant These measurements showed that this method has potential to monitor many dynamic situations in processing plants such as in a continuous dissolver or batch dissolvers either to obtain the neutron multiplication factor k or to be used as a signature to verify that various processes are occurring in a repeatable or bounded way. This verification of normal operation would be by comparing noise analysis signatures for the process with reference signatures. Abnormal operation could be ascertained if the signature deviates by some specified amount from the reference signatures from normal operation. The deviations from normal could be specified by measurement or by Monte Carlo neutron transport theory methods directly calculating the measured parameters for the processing plant applications.

The Westcott g-factors, which allow the user to determine reaction rates for nuclear reactions taking place at various temperatures, have been calculated using data from the Evaluated Neutron Nuclear Data library, ENDF-VI. The nuclides chosen have g-factors which are significantly different from unity and result in different reaction rates compared to nuclides whose neutron capture cross section varies as the reciprocal of the neutron`s velocity. Values are presented as a function of temperature up to 400{degrees}C.

The SLAC-based NLC working group has been considering issues relevant to the operation of an X-band 0.5--1.0 TeV collider. This report summarizes some of the results the group has achieved to date. The NLC will collide trains of closely spaced bunches of 10{sup 10} particles. Typical parameters are 1.4 ns for the inter-bunch spacing, 100 bunches/train, and 180 trains/sec. Its final focus (FF) will provide spot sizes at the interaction point (IP) of dimensions {sigma}{sub x} = 300--400 nm, {sigma}{sub y} = 2--3 nm, and {sigma}{sub z} = 100 {mu}m. The closely spaced bunches and the desire to have each bunch interact only with its partner imply that there must be a crossing angle to the IP. The high charge density will cause backgrounds due to electromagnetic beam-beam interactions and particle detectors with good timing resolution will be required to separate hits from the interaction causing the trigger from the background hits arising from other bunches in the train. The 2 nm beam spots will challenge experimenters to get and keep the beams in collision. They will require special consideration to be given to issues of alignment, ground motion, and vibrations induced by the transfer of cooling fluids. The detector …

Before the cancellation of the New Production Reactor Programs for the production of tritium, the reactors and associated processing were being designed to contain some of the most highly automated and remote systems conceived for a Department of Energy facility. Integrating safety, security, materials control and accountability (MC and A), and process systems at the proposed facilities would enhance the overall information and protection-in-depth available. Remote, automated fuel handling and assembly/disassembly techniques would deny access to the nuclear materials while upholding ALARA principles but would also require the full integration of all data/information systems. Such systems would greatly enhance MC and A as well as facilitate materials tracking. Physical protection systems would be connected with materials control features to cross check activities and help detect and resolve anomalies. This paper will discuss the results of a study of the safeguards and security benefits achieved from a highly automated and integrated remote nuclear facility and the impacts that such systems have on safeguards and computer and information security.

The California Institute for Energy efficiency`s third annual conference highlights the results of CIEE-sponsored multiyear research in three programs: Building Energy Efficiency, Air Quality Impacts of Energy Efficiency, and End-Use Resource Planning. Results from scoping studies, Director`s discretionary research, and exploratory research are also featured.

The Paducah Gaseous Diffusion Plant (PGDP), owned by the US Department of Energy (DOE) and operated under contract by Martin Marietta Energy systems, Inc., is located southwest of Paducah, Kentucky. An aerial photograph and an oblique sketch of the plant are shown in Figures 1 and 2, respectively. The fenced portion of the plant consists of 748 acres. This plant was constructed in the 1950`s and is one of only two gaseous diffusion plants in operation in the United States; the other is located near Portsmouth, Ohio. The facilities at PGDP are currently being evaluated for safety in response to natural seismic hazards. Design and evaluation guidelines to evaluate the effects of earthquakes and other natural hazards on DOE facilities follow probabilistic hazard models that have been outlined by Kennedy et al. (1990). Criteria also established by Kennedy et al. (1990) classify diffusion plants as ``moderate hazard`` facilities. The US Army Engineer Waterways Experiment Station (WES) was tasked to calculate the site response using site-specific design earthquake records developed by others and the results of previous geotechnical investigations. In all, six earthquake records at three hazard levels and four individual and one average soil columns were used.

At the Hanford Site, the record of decision for remediation of CERCLA sites is largely based on results of the baseline risk and performance assessment of the remedial action alternatives. These assessments require the ability to predict the fate and transport of contaminants along appropriate exposure pathways which, in case of the Hanford Site, includes the migration of contaminants through the vadose zone to the water table. Listed below are some of the requirements, as prescribed by the regulators, relative to CERCLA risk and performance assessment at Hanford. A workshop was organized by the Environmental Risk and Performance Assessment Group, Westinghouse Hanford Company on March 29--30, 1993 at the Richland Best Western Tower Inn. During the workshop, an assessment was made of the need for and scope of various tasks being conducted or planned as part of the Hanford Site waste isolation performance assessment/risk assessment activities. Three external, nationally-recognized experts served as part of a review panel for the workshop: (a) Professor Lynn Gelhar of MIT; (b) Professor Peter Wierenga of University of Arizona; and (c) Dr. Rien van Genuchten of US Salinity Laboratory, Riverside, California. The technical experts provided their perspectives on the current state-of-the-art in vadose zone flow …

Sandia has developed an advanced operational control system approach, called Graphical Programming, to design and operate robot systems in unstructured environments. This Graphical Programming approach produces robot systems that are faster to develop and use, safer in operation, and cheaper overall than altemative teleoperation or autonomous robot control systems. This approach uses 3-D visualization and simulation software with intuitive operator interfaces for the programming and control of complex robotic systems. Supervisor software modules allow an operator to command and simulate complex tasks in a graphic preview mode and, when acceptable, command the actual robots and monitor their motions with the graphic system. Graphical Programming Supervisors maintain registration with the real world and allow the robot to perform tasks that cannot be accurately represented with models alone by using a combination of model and sensor-based control. All of these capabilities when combined result in a flexible system which is readily able to meet the demands called for in construction automation. This paper describes the Graphical Programming approach, several example control systems that use Graphical Programming, key features necessary for implementing successful Graphical Programming systems, and specific examples of applying these systems to robotic operations.

The mission of the US Department of Energy (DOE) has changed from defense production of special nuclear materials to cleanup of production facilities at the Hanford Site. The DOE contractors have formed the Energy Facility Contractors Group to support this change in mission. In addition, the Safety Analysis Working Subgroup for Environmental Restoration and Decontamination and Decommissioning (ER/D&D) was formed to identify, develop, and share information that supports safety analyses and engineering of ER/D&D activities. Safety analysis is in part the process of identifying and understanding the hazards that could result in exposures to radiological or chemical hazardous substances. The following paragraphs address the special considerations given to hazard characterization for ER/D&D activities.

This quarterly report covers activities of Catalytic Multi-Stage Liquefaction of Coal during the period January 1--March 31, 1993, at Hydrocarbon Research, Inc. in Lawrenceville and Princeton, New Jersey. This DOE contract period is from December 8, 1992 to December 7, 1994. The overall objective of the program is to produce liquid fuels from direct coal liquefaction at a cost that is competitive with conventional fuels. Specifically, this continuous bench-scale program contains provisions to examine new ideas in areas such as: low temperature pretreatments, more effective catalysts, on-line hydrotreating, new coal feedstocks, other hydrogen sources, more concentrated coal feeds and other highly responsive process improvements while assessing the design and economics of bench-scale results. The quarterly report covers work on Laboratory Scale Studies, Continuous Bench-Scale Operations, Technical Assessment and Project Management.

The Federal Fleet Conversion Task Force was created by Executive Order 12844, signed by President Clinton on April 21, 1993. In the Order, the President directed that purchases of alternative fueled vehicles by the Federal Government be substantially increased beyond the levels required by current law. The President charged the Task Force with developing recommendations for carrying out the Executive Order, with special emphasis on setting a course that will lead to the widespread use of alternative fueled vehicles by Federal, State, and local government fleets, by private fleets and, ultimately, by individuals. The chief recommendation of the Task Force is the establishment of a Presidential Clean Cities Initiative. To support creation of the Presidential Initiative, the Task Force identified 38 cities and regions, prioritized into three tiers, for concentrating the Initiative`s efforts in Fiscal Years 1994 through 1996. This concentration of effort is key to the effectiveness of the Initiative. The 38 cities and regions would receive priority funding for Federal vehicle purchases and for infrastructure development. In addition, the Task Force has made specific recommendations for overcoming numerous regulatory, economic, and technical barriers that have slowed the introduction of alternative fueled vehicles into general use.

The Fast Flux Test Facility (FFTF) surveillance program provides coupon surveillance materials that are irradiated to the expected lifetime damage dose that the represented component will experience. This methodology requires a knowledge of the damage dose rates to the surveillance assemblies and to the critical locations of the structural components. This analysis updates the predicted exposures from a total fluence to a displacement per atom (dpa) basis using Monte Carlo (computer code for) neutron photon (transport) code (MCNP). The MCNP calculation improves the relative consistency and lowers the predicted damage rates uncertainty in a number of out-of-core locations. The results were used an part of the evaluation to extend the lifetime of the invessel components to 30 years in support of multiple missions for FFTF.

An analysis is carried out to determine the effects of the diffusional resistance on the rate of the adsorption of ammonia in an aqueous solution. A performance prediction model is developed to calculate the local rate of heat and mass transfer, including physical and thermodynamic property calculations of the mixture. An algorithm is developed for calculating the interfacial conditions. The local heat- and mass-transfer calculation is then incorporated into the performance prediction method for adsorption for a given geometry.

This strategy plan describes a coupled analytical/experimental approach to develop a multi-functional scarifier end effector coupled with a pneumatic conveyance system to retrieve wastes from underground storage tanks. The scarifier uses ultra-high-pressure water jets to rubblize and entrain waste forms such as salt cake, sludge, and viscous liquid that can be transported pneumatically. The three waste types (hard, brittle, salt cake, viscous liquid, and deformable sludge) present increasingly complex challenges for scarification and pneumatic conveyance. Salt cake is anticipated to be the easiest to retrieve because (1) a theoretical model of hydraulic rock fracture can be applied to estimate jet performance to fracture salt cake, and (2) gas-solids transport correlations can be used to predict pneumatic transport. Deformable sludge is anticipated to be the most difficult to retrieve: no theories, correlations, or data exist to predict this performance. However order-of-magnitude gas-solid correlations indicate particulate wastes of prototypic density can be transported to a height of 20 m within allowable pressure limits provided that the volume fraction of the gaseous phase is kept above 95%. Viscous liquid is anticipated to be of intermediate complexity to retrieve. Phenomena that are expected to affect system performance are ranked. Experiments and analyses necessary to …

These Appendices describe various technologies that may be applicable to the Mixed Waste Treatment Plant (MWTP) Chemical/Physical Treatment System (CPTS). These technologies were identified by the CPTS Technical Support Group (TSG) as potentially applicable to a variety of separation, volume reduction, and decontamination requirements. The purpose was to identify all available and developing technologies, and their characteristics, for subsequent evaluation for specific requirements identified for the CPTS. However, the technologies described herein are not necessarily all inclusive, nor are they necessarily all applicable.

This paper describes fluid-structure-interaction and structure response analyses of a reactor vessel subjected to loadings associated with postulated accidents, using the improved hybrid Lagrangian-Eulerian code ALICE-II. The objective of the present analyses is to study the cover response and potential for missile generation in response to a fuel-coolant interaction in the core region. Three calculations were performed using the cover weight as a parameter. To study the effect of the cavity water outside the reactor vessel, vessel response calculations for both wet- and dry-cavity designs are compared. Results indicate that for all cases studied and for the design parameters assumed, the calculated cover displacements are all smaller than the bolts` ultimate displacement and no missile generation of the closure head is predicted. Also, solutions reveal that the cavity water of the wet-cavity design plays an important role of restraining the downward displacement of the bottom head. Based on these studies, the analyses predict that the structure integrity is maintained throughout the postulated accident for the wet-cavity design.

Progress reports are presented for the following fuels researches: Development of analytical methodology for analysis of heave crudes; and thermochemistry and thermophysical properties of organic nitrogen and diheteroatom-containing compounds. Some of the accomplishments are: Topical reports summarizing GC/MS methodology for determination of amines in petroleum and catalytic cracking behavior of compound type in Wilmington 650{degrees} F+ resid were completed; density measurements between 320 K and 550 K were completed for 8-methylquinoline; high-temperature heat-capacities and critical temperature (near 800 K) for 8-methylquinoline were determined; vapor-pressure measurements were completed for 2,6-dimethylpyridine; and a series of enthalpy-of-combustion measurement was completed for 1,10-phenanthroline, phenazine, 2-methylquinoline, and 8-methylquinoline.

Radon in indoor air may cause the exposure of the public to excessive radioactivity. Radiolysis of water vapor in indoor air due to radon decay could produce ({center_dot}OH and HO{sub 2} {center_dot}) that may convert atmospheric constituents to compounds of lower vapor pressure. These lower vapor pressure compounds might then nucleate to form new particles in the indoor atmosphere. Chemical amplification was used to determine HO{sub x}{center_dot} production rate in indoor air caused by radon decay. Average HO{sub x}{center_dot} production rate was found to be (4.31{plus_minus}0.07) {times} 10{sup 5} HO{sub x}{center_dot} per Rn decay per second (Bq) 3.4 to 55.0% at 22C. This work provided G{sub (HO{sub x}{center_dot})}-value, 7.86{plus_minus}0.13 No./100 eV in air by directly measuring [HO{sub x}{center_dot}] formed from the radiolysis procedure. This G value implies that HO{sub x}{center_dot} produced by radon decay in air might be formed by multiple processes and may be result of positive ion-molecule reactions, primary radiolysis, and radical reactions. There is no obvious relation between HO{sub x}{center_dot} production rate and relative humidity. A laser-induced fluorescence (LIF) system has been used for {center_dot}OH production rate measurement; it consists of an excimer laser, a dye laser, a frequency doubler, a gaseous fluorescence chamber, and other optical …

Assuring the safe operation of a nuclear power plant depends, to a large extent, on how effectively one understands and manages the aging-related degradation that occurs in structures, systems, and components (SSCs). Aging-related degradation is typically managed through a nuclear plant`s maintenance program. A review of 44 Maintenance Team Inspection (MTI) Reports indicated that while some plant organizations appeared to assume a proactive mode in preventing aging-related failures of their SSCs important to safety, others seemed to be taking a passive or reactive mode. Across all plants, what is clearly needed, is a strong recognition of the importance of aging-related degradation and the use of existing organizational assets to effectively detect and mitigate those effects. Many of those assets can be enhanced by the consideration of organizational and management factors necessary for the implementation of an effective aging management program. This report provides a discussion of this program.

Shock-compression recovery experiments were performed on mixtures of Ti and Si powders of fine, medium, and coarse morphology, and packed at different initial densities, using the Sandia Momma and Poppa Bear fixtures with Baratol explosive. The shock-compressed configuration revealed characteristics typical of either chemically reacted material with fine equiaxed grains, or unreacted material with densely packed Ti and Si particles. The unreacted configuration showed that Ti particles were extensively deformed, irrespective of powder morphology and shock conditions generated by either fixture. In contrast Si particles showed different characteristics depending on the powder morphology, packing density, and shock conditions. The microstructural characteristics of unreacted configuration of Ti and Si powder mixtures were investigated. Mechanistic processes occurring prior to the inception of shock-induced chemical reactions in this system are described.

This paper presents the outgassing rates of two commercially available multi-layer insulation (MLI) materials commonly used in cryogenic applications. Both Reemay Spunbonded Polyester and DuPont Double Aluminized Mylar (DAM) were studied for outgassing species and respective rates, and the total amount of outgassed material. Measurements were made using a Fixed Aperture Technique. A sample was pumped on through an aperture of known size with a turbomolecular pump. Pressure vs. time was plotted for both Reemay and DAM, as well as the baseline system, and data conveniently extrapolated to {approx}1,000 hrs. A quadrupole residual gas analyzer was used to measure the outgassing species.

The unique coordination of the copper ions in +1, +2, and +3 oxidation states which are stable in a range of oxygen partial pressure, 10{sup {minus}6} < P(O{sub 2}) < 10{sup 3} atm, makes possible the formation of a wide variety of distinct structures. By controlling the oxygen pressure during the synthesis and annealing, the distribution of metal- and oxygenions can be modified on an atomic scale to optimize the structural and electronic properties. We present several examples of compounds for which the critical structural elements for superconductivity, i.e. the perfectly ordered CuO{sub 2}-planes, have been obtained and doped with holes by means of high oxygen pressure, P(O{sub 2}) > 1 atm. These materials, La{sub 2}CuO{sub 4+{delta}}, La{sub 2-x}Ca{sub x}CuO{sub 4} and YSr{sub 2-x}La{sub x}Cu{sub 3}O{sub 7+{delta}} offer a unique opportunity to study the relationship between superconductivity and structural, magnetic and chemical properties.

This report identifies important environment, health, and safety issues associated with nickel metal-hydride (Ni-MH) batteries and assesses the need for further testing and analysis. Among the issues discussed are cell and battery safety, workplace health and safety, shipping requirements, and in-vehicle safety. The manufacture and recycling of Ni-MH batteries are also examined. This report also overviews the ``FH&amp;S`` issues associated with other nickel-based electric vehicle batteries; it examines venting characteristics, toxicity of battery materials, and the status of spent batteries as a hazardous waste.

The technology for pulsed power based high average power accelerators is being developed in the RHEPP (Repetitive High Energy Pulsed Power) project. This technology base uses magnetic pulse compression to generate repetitive, high peak power pulses. The 1 {mu}s pulse compressor accepts 3400 V rms, 120 Hz input power from a 600-kW alternator and delivers unipolar {approximately}1 {mu}s rise time, 260 kV pulses to the RHEPP pulse forming line at a rate of 120 pps. The compressor consists of 5 stages of pulse compression with a 15 to 260 kV step up transformer between stages 2 and 3. Magnetic switches are used throughout the compressor because such switches seem to offer the potential of meeting the lifetime requirements of high average power systems. Thermal and electrical data has been acquired to characterize the compressor during several long duration runs (some over 1 million shots). A description of the compressor and its components along with data and a discussion of the compressors performance are presented.