The overall objective of the work on Task 003 of Subcontract 9-X52-W7423-1 was to provide LANL with support to the DOE Defense Program (DP) Safety Programs. The effort included the identification of appropriate safety requirements, the refinement of a DP-specific Safety Analysis Report (SAR) Format and Content Guide (FCG) and Comprehensive Review Plan (CRP), incorporation of graded approach instructions into the guidance, and the development of a safety analysis methodologies document. All tasks which were assigned under this Task Order were completed. Descriptions of the objectives of each task and effort performed to complete each objective is provided here.

Low rank approximation of large and/or sparse rectangular matrices is a very import ant topic in many application problems and is closely related to the sin- gular value decomposition of the matrices. In this paper, we propose an implicit restart scheme for the bidiagonal Lanczos algorithm to compute a subset of the dominating singular triplets. We also illustrate the connection of the method with inverse eigenvalue problems. In the Lanczos process, we use the so-called one-sided reorthogonalization strategy to maintain the orthogonality level of the Lanczos vec- tors. The efficiency and the applicability of our algorithm are illustrated by some numerical examples from information retrieval applications.

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. LANL has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. This includes receipt and storage of PuO{sub 2} powder, fabrication of MOX fuel pellets, assembly of fuel rods and bundles, and shipping of the packaged fuel to a commercial reactor site. Support activities will take place within both Category 1 and 2 areas. Technical Area (TA) 55/Plutonium Facility 4 will be used to store the bulk PuO{sub 2} powder, fabricate MOX fuel pellets, assemble rods, and store fuel bundles. Bundles will be assembled at a separate facility, several of which have been identified as suitable for that activity. The Chemistry and Metallurgy Research Building (at TA-3) will be used for analytical chemistry support. Waste operations will be conducted in TA-50 and TA-54. Only very minor modifications will be needed to accommodate …

The Lorentz-operator form of relativistic quantum mechanics, with relativistic wave equation i{h_bar}{partial_derivative}{psi}/{partial_derivative}t=(mc{sup 2}{gamma}+e{Phi}){psi}, is implemented to guarantee a single-energy root. The Lorentz factor as modified by Pauli's ansatz is given by {gamma}={radical}1+[{rvec {sigma}}{center_dot}(i{h_bar}{rvec {del}}+(e/c){rvec A})]{sup 2}/m{sup 2}c{sup 2}, such that the theory is appropriate for electrons. Magnetic fine structure in the Lorentz relativistic wave equation emerges on the use of an appropriate operator form of the Lienard-Wiechert four- potential ({Phi},{rvec A}) from electromagnetic theory. Although computationally more intensive the advantage of the theory is the elimination of the negative-root of the energy and an interpretation of the wave function based on a one-particle, positive definite probability density like that of nonrelativistic quantum mechanics.

This report describes the results of an analysis to determine the economic and operational value of battery storage to wind and photovoltaic (PV) generation technologies to the Sacramento Municipal Utility District (SMUD) system. The analysis approach consisted of performing a benefit-cost economic assessment using established SMUD financial parameters, system expansion plans, and current system operating procedures. This report presents the results of the analysis. Section 2 describes expected wind and PV plant performance. Section 3 describes expected benefits to SMUD associated with employing battery storage. Section 4 presents preliminary benefit-cost results for battery storage added at the Solano wind plant and the Hedge PV plant. Section 5 presents conclusions and recommendations resulting from this analysis. The results of this analysis should be reviewed subject to the following caveat. The assumptions and data used in developing these results were based on reports available from and interaction with appropriate SMUD operating, planning, and design personnel in 1994 and early 1995 and are compatible with financial assumptions and system expansion plans as of that time. Assumptions and SMUD expansion plans have changed since then. In particular, SMUD did not install the additional 45 MW of wind that was planned for 1996. Current SMUD …

A granular activated carbon (GAC) system is now in operation at Pantex to treat groundwater from the perched aquifer that is contaminated with high explosives. The main chemicals of concern are RDX and HMX. The system consists of two GAC columns in series. Each column is charged with 10,000 pounds of Northwestern LB-830 GAC. At the design flow rate of 325 gpm, the hydraulic loading is 6.47 gpm/ft{sup 2}, and the empty bed contact time is 8.2 minutes per column. Currently, the system is operating at less than 10% of its design flow rate, although flow rate increases are expected in the relatively near future. This study had several objectives: Estimate the service life of the GAC now in use at Pantex; Screen several GACs to provide a recommendation on the best GAC for use at Pantex when the current GAC is exhausted and is replaced; Determine the extent to which natural organic matter in the Pantex groundwater fouls GAC adsorption sites, thereby decreasing the adsorption capacity for high explosives; and Determine if computer simulation models could match the experimental results, thereby providing another tool to follow system performance.

Plans for disposing of the high-level radioactive wastes at the Hanford Site call for retrieving, pretreating, and finally immobilizing the wastes in a glass matrix. Since the cost for vitrifying and disposing of high-level wastes will be very great, pretreatment processes are being developed to reduce their volume. The baseline method for pretreating Hanford tank sludges is caustic leaching. Earlier studies with Hanford tank-sludge simulants and with actual Hanford tank sludges have indicated that treating water-washed and caustic-leached solids with oxidants can significantly increase the removal of Cr. Permanganate and ozone have been shown to be generally the most rapid and effective chemical agents for this purpose. The work described in this report continues to examine the effectiveness of solubilizing additional Cr from Hanford tank wastes by oxidation of the water-insoluble solids from tanks U-108, U-109, and SX-108 under alkaline conditions. The current study confirms that permanganate is highly effective at removing chromium from water solids under alkaline conditions, with Cr removals of up to 99+%. Elemental oxygen can also be highly effective, with removals up to 97+%.

This report presents the results of field testing a horizontal well recirculation system at the Portsmouth Gaseous Diffusion Plant (PORTS). The recirculation system uses a pair of horizontal wells, one for groundwater extraction and treatment and the other for reinjection of treated groundwater, to set up a recirculation flow field. The induced flow field from the injection well to the extraction well establishes a sweeping action for the removal and treatment of groundwater contaminants. The overall purpose of this project is to study treatment of mixed groundwater contaminants that occur in a thin water-bearing zone not easily targeted by traditional vertical wells. The project involves several research elements, including treatment-process evaluation, hydrodynamic flow and transport modeling, pilot testing at an uncontaminated site, and pilot testing at a contaminated site. The results of the pilot test at an uncontaminated site, the Clean Test Site (CTS), are presented in this report.

We have developed and evaluated a carbon filter to remove dimethyl sulfoxide (DMSO) vapor from the exhaust of the W79 HE (high explosive) Dissolution Workstation. A series of laboratory tests were conducted on eight different carbon samples to establish the vapor breakthrough curves and to select the best sample. Empirical equations were developed to predict the breakthrough curve for various air flows and bed thickness, These equations were used to design the filter cartridge. The filter consists of a cylindrical cartridge 12 inches high and 6 and 10 inches inside and outside diameter and has a pressure drop of 0.8 inches of water at 50 cfm. Experiments and computations verified the efficiency of the filter cartridge is greater than 99% at 35 cfm, and the carbon filter can process 60 HE assemblies while maintaining greater than 90% efficiency before the carbon must be replaced.

Bulk Bi{sub 2}Sr{sub 2}CaCu{sub 2}O{sub 8+{delta}} (Bi2212) bicrystals containing a single high quality [001] twist grain boundary junction were prepared in order to investigate the orbital symmetry of the superconducting order parameter in highly anisotropic Bi-based high temperature superconductors. The misorientation angles of the bicrystals ranged from 0 to 180{degree}. The microstructure in the vicinity of the junction was characterized using high-resolution, nano-probe analytical microscopy. The authors found that some high angle twist junctions were able to carry a critical current density similar to their constituent single crystals. These results cannot be interpreted in terms of a pure d{sub x{sup 2}{minus}y{sup 2}}-wave order parameter for superconducting Bi2212.

This Cooperative Research and Development Agreement (CRADA) report deals with the development of nickel aluminide alloy for improved longer life heat-resistant fixture assemblies for batch and continuous pusher carburizing furnaces. The nickel aluminide development was compared in both coupon and component testing with the currently used Fe-Ni-Cr heat-resisting alloy known as HU. The specific goals of the CRADA were: (1) casting process development, (2) characterization and possible modification of the alloy composition to optimize its manufacturing ability and performance under typical furnace operating conditions, and (3) testing and evaluation of specimens and prototype fixtures. In support of the CRADA objectives, coupons of nickel aluminide and the HU alloy were installed in both batch and pusher furnaces. The coupons were taken from two silicon levels and contained welds made with two different filler compositions (IC-221LA and IC-221W). Both nickel-aluminide and HU coupons were removed from the batch and pusher carburizing furnace at time intervals ranging from one month to one year. The exposed coupons were cut and mounted for metallographic, hardness, and microprobe analysis. The results of the microstructural analysis have been transmitted to General Motors Corporation, Saginaw Division (Delphi Saginaw) through reports that were presented at periodic CRADA review meetings. …

This report describes preliminary work leading to the development of an innovative technology for treating a mixed waste problem at Los Alamos National Laboratory (LANL). The specific problem being addressed by this research is the result of research activity at the Meson Physics Facility (LAMPH). The LAMPH facility conducts high energy neutron research. Lead BB`s were placed in containers and used as shielding during experiments.This lead was stored in piles on the ground when it was not in use, and it sometimes sat for extended periods of time, perhaps as long as 20 years. The lead was mobilized overtime, and contaminated the underlying soil. Because of the neutron bombardment, a portion of the lead {sup 207}Pb became radioactive {sup 210}Pb, and the lead became both a listed waste and radioactive, which classified it as a mixed waste. The contaminated soil has been removed from the site and placed in drums for storage until a suitable treatment technology can be identified. The contents of the barrels consists of a mixture of lead contaminated soil and lead BB`s.

A preliminary radiological survey was conducted at Utirik Atoll in 1978 as part of the Northern Marshall Islands Radiological Survey (NMIRS). A dose assessment based on these limited data indicated a relatively low dose of about 0.12 mSv to people living on Utirik in 1978 (Robison et al., 1982). A much more detailed radiological survey was conducted in April of both 1993 and 1994. Aerial photos of the islands of Utirik Atoll were taken as part of the 1978 NMIRS. The sampling grids for the 1993 and 1994 surveys are shown overlaid on these aerial photos in Figures 1, 2, 3, and 4. External gamma measurements and a collection of either drinking coconuts or copra coconuts were made at each location. Pandanus, breadfruit, lime, and banana were collected where available. Ground water was collected in 1993/94 from four wells on Utirik Island and two wells on Aon Island. Surface soil and soil profiles were collected at some of the grid points on each of the islands at the atoll in 1993/94. A comparison of the number of samples collected in 1978 and 1993/94 are shown in Table 1. A detailed listing of the samples collected in the 1993/94 radiological survey …

The extraction of the SPICE netlist form MAGIC based layouts is investigated. It is assumed that the layout is fully coherent with the corresponding mask representation. The process of the extraction can be made in three steps: (1) extraction of .EXT file from layout, through MAGIC command extract; (2) extraction of the netlist from .EXT file through ext2spice extractor; and (3) correction of the netlist through ext2spice.corr program. Each of these steps introduces some approximations, most of which can be optimized, and some errors, most of which can be corrected. Aim of this work is the description of each step, of the approximations and errors on each step, and of the corresponding optimizations and corrections to be made in order to improve the accuracy of the extraction. The HP AMOS14TB 0.5 {micro}m process with linear capacitor and silicide block options and the corresponding SCN3MLC{_}SUBM.30.tech27 technology file will be used in the following examples.

On October 15, 1997, the Cassini spacecraft was launched from Cape Canaveral Air Station (CCAS) and is now on its way to the planet Saturn. The functional support provided to NASA by DOE included the Advance Launch Support Group (ALSG). If there had been a launch anomaly, the ALSG would have provided a level of radiological emergency response support adequate to transition into a Federal Radiological Monitoring and Assessment Center (FRMAC). Additional functional radiological emergency response support, as part of the ALSG, included the: (1) Aerial Measurement System (AMS); (2) Atmospheric Release Advisory Capability (ARAC); (3) Geographic Information System (GIS); (4) Emergency Response Data System (ERDS); (5) Radiation Emergency Assistance Center and Training Site (REAC/TS); (6) Field monitoring and sampling; (7) Radioanalysis via RASCAL; (8) Source recovery; and (9) Neutron dosimetry and communications support. This functional support provided the capability to rapidly measure and assess radiological impacts from a launch anomaly. The Radiological Control Officer (RCO) on KSC established a Radiological Control Center (RADCC) as the focal point for all on-site and off-site radiological data and information flow. Scientists and radiological response personnel located at the RADCC managed the field monitoring team on the KSC/CCAS federal properties. Off-site radiological emergency …

Generation of free carriers in a semiconductor gives rise to mechanical stress. Photo-induced stress phenomena in MEMS micro-structures can be used in the room temperature detection of infrared photons. Choice of the appropriate semiconductor material for the MEMS micro-structures determines the cutoff wavelength of the uncooled infrared photon detector. The authors have measured the deflection of silicon and indium antimonide micro-structures resulting from a photo-induced stress. The excess charge carriers responsible for the photo-induced stress were produced via photon irradiation from both a diode laser and a black body source. In the case of Si, the photo-induced stress is of opposite direction and about four times larger than the thermal stress. For indium antimonide the direction of stress is the same as due to thermal effects. The photo-induced stress can be distinguished from the thermal stress based on the cut-off wavelength, response speed, and perhaps the direction of the microstructure deflection.

Alternative refrigerants are being developed by industry to prevent the further destruction of stratospheric ozone by chlorofluorocarbons (CFCs), which had been the working fluids of choice for many air-conditioning and refrigeration machines. Hydrofluorocarbons (HFCs) are one class of compounds that are being pursued as replacements because their ozone depletion potential is zero. In general, the exchange of fluorine atoms on an HFC molecule with hydrogen atoms decreases its atmospheric lifetime, and it may also increase the efficiency of the working fluid. Both of these effects are highly desirable from environmental considerations since they act to mitigate global warming. Unfortunately, more hydrogen on a HFC is usually associated with an increase in flammability. An accepted method for determining the flammability limits of gaseous fuels is ASTM Standard E 681. The minimum and maximum concentrations of the fuel in air for flame propagation are based upon the observed ignition and growth of a flame in a vessel filled with a quiescent fuel/air mixture. a Clear distinction is sought between a non-propagating flicker and a flame which has enough horizontal propagation to be hazardous. This report reviews the past work done on premixed, counter-flowing flames, describes the current counter-flow burner facility and operating …

To verify that exposures resulting from operations at Department of Energy (DOE) nuclear facilities remain very small, each site at which nuclear activities are conducted operates an environmental surveillance program to monitor the air, water and any other pathway whereby radionuclides from operations might conceivably reach workers and members of the public. Environmental surveillance and monitoring results are reported annually to the DOE-Headquarters. This report presents a compilation of data collected in 1997 for the routine environmental surveillance programs conducted on and around the Idaho National Engineering and Environmental Laboratory (INEEL). The results of the various monitoring programs for 1997 indicated that radioactivity from the INEEL operations could generally not be distinguished from worldwide fallout and natural radioactivity in the region surrounding the INEEL. Although some radioactive materials were discharged during INEEL operations, concentrations in the offsite environment and doses to the surrounding population were far less than state of Idaho and federal health protection guidelines.

Preliminary designs are described for models of the interaction of Zircaloy and hydrogen and the consequences of this interaction on the behavior of fuel rod cladding during severe accidents. The modeling of this interaction and its consequences involves the modeling of seven processes: (1) diffusion of oxygen from the bulk gas into the boundary layer at the external cladding surface, (2) diffusion from the boundary layer into the oxide layer at the cladding external surface, (3) diffusion from the inner surface of the oxide layer into the metallic part of the cladding, (4) uptake of hydrogen in the event that the cladding oxide layer is dissolved in a steam-starved region, (5) embrittlement of cladding due to hydrogen uptake, (6) cracking of cladding during quenching due to its embrittlement and (7) release of hydrogen from the cladding after cracking of the cladding. An integral diffusion method is described for calculating the diffusion processes in the cladding. Experimental and theoretical results are presented that show the uptake of hydrogen in the event of dissolution of the oxide layer occurs rapidly and that show the release of hydrogen in the event of cracking of the cladding occurs rapidly. These experimental results are used …

This project was initiated in October 1990, with the objective of developing and validating a new computer model of a recovery boiler furnace using a computational fluid dynamics (CFD) code specifically tailored to the requirements for solving recovery boiler flows, and using improved submodels for black liquor combustion based on continued laboratory fundamental studies. The key tasks to be accomplished were as follows: (1) Complete the development of enhanced furnace models that have the capability to accurately predict carryover, emissions behavior, dust concentrations, gas temperatures, and wall heat fluxes. (2) Validate the enhanced furnace models, so that users can have confidence in the predicted results. (3) Obtain fundamental information on aerosol formation, deposition, and hardening so as to develop the knowledge base needed to relate furnace model outputs to plugging and fouling in the convective sections of the boiler. (4) Facilitate the transfer of codes, black liquid submodels, and fundamental knowledge to the US kraft pulp industry. Volume 2 contains the last section of Appendix I, Radiative heat transfer in kraft recovery boilers, and the first section of Appendix II, The effect of temperature and residence time on the distribution of carbon, sulfur, and nitrogen between gaseous and condensed phase …

The authors are continuing to use the computational fluid dynamics code CFX-4.2 to evaluate the steady-state thermal-hydraulic conditions in the Nuclear Material Storage Facility Renovation Title 1 60% Design. The analyses build on those performed for the 30% design. They have run an additional 9 cases to investigate both the performance of the passive vault and of an individual drywell. These cases investigated the effect of wind on the inlet tower, the importance of resolving boundary layers in the analyses, and modifications to the porous-medium approach used in the earlier analyses to represent better the temperature fields resulting from the detailed modeling of the boundary layers. The difference between maximum temperatures of the bulk air inside the vault for the two approaches is small. They continued the analyses of the wind effects around the inflector fixture, a canopy and cruciform device, on the inlet tower by running a case with the wind blowing diagonally across the inflector. The earlier analyses had investigated a wind that was blowing parallel to one set of vanes on the inflector. Several subcases for these analyses investigated coupling the analysis to the facility analysis and design changes for the inflector.

This document provides a report and an analysis of the Radiological Control Program through the second quarter of Calendar Year 1998 (CY-98) for Lockheed Martin Idaho Technologies Company (LMITCO). LMITCO is the prime contractor at the Idaho National Engineering and Environmental Laboratory (INEEL). This Performance Indicator Report is provided in accordance with Article 133 of the INEEL Radiological Control Manual. The INEEL collective occupational radiation deep dose is 30.757 person-rem year to date, compared to a year to date goal of 47.0 person-rem. Overall, the site dose goal has been reduced. This is mainly due to work scope reductions at the Idaho Nuclear Technologies and Engineering Center (INTEC). However, due to unforeseen increases in shipments to the Radioactive Waste Management Complex, their goal has been raised to 9.60 person-rem to accommodate the increase in dose. The RWMC increase results in an increase to the LMITCO goal to 100.76f person-rem. The goal is not plotted in a linear fashion since work scope varies from quarter to quarter.

The Center for Accelerator Mass Spectrometry (CAMS) in the Earth and Environmental Sciences Directorate at Lawrence Livermore National Laboratory (LLNL) operates two accelerators and is in the process of installing two new additional accelerators in support of a variety of basic and applied measurement programs. To monitor the radiation environment in the facility in which these accelerators are located and to terminate accelerator operations if predetermined radiation levels are exceeded, an updated computer controlled radiation monitoring system has been installed. This new system also monitors various machine safety interlocks and again terminates accelerator operations if machine interlocks are broken. This new system replaces an older system that was originally installed in 1988. This paper describes the updated B190 computer controlled radiation monitoring and safety interlock system.

The mission at the Savannah River Site has changed from the production of nuclear weapons materials for national defense to the management of waste, restoration of the environment, and the development of industry in and around the site.