This report, provided annually, summarizes monitoring data collected to assess Strategic Petroleum Reserve (SPR) impacts on the environment. The report serves as a management tool for mitigating such impacts, thus serving the public interest by ensuring environmentally sound operation of the Strategic Petroleum Reserve (SPR). Included is a description of each site's environment, an overview of the SPR environmental program, and a recapitulation of special environmental activities and events associated with each SPR site during 1989. The active permits and the results of the environmental monitoring program (i.e., air, surface water, groundwater, and waste discharges) are discussed by site. The quality assurance program is presented which includes results from laboratory and field audits and studies performed internally and by regulatory agencies. In general, no significant adverse environmental impact resulted from SPR activities during 1989, except for a brine release from a pipeline perforation south of the Bryan Mound site adversely affecting a small area of marsh vegetation which is recovering at this time. 22 refs., 15 figs., 17 tabs.

This report discusses the research being conducted at Lawrence Berkeley Laboratory's Accelerator and Fusion Research Division. The main topics covered are: heavy-ion fusion accelerator research; magnetic fusion energy; advanced light source; center for x-ray optics; exploratory studies; high-energy physics technology; and bevalac operations.

This paper discusses: accelerator physics and special projects; experiments and injectors; magnetic optics and beam diagnostics; accelerator design and engineering; radio-frequency technology; accelerator theory and simulation; free-electron laser technology; accelerator controls and automation; and high power microwave sources and effects.

A Level II/III probabilistic risk assessment (PRA) has been performed for N Reactor, a Department of Energy (DOE) production reactor located on the Hanford reservation in Washington. The accident progression analysis documented in this report determines how core damage accidents identified in the Level I PRA progress from fuel damage to confinement response and potential releases the environment. The objectives of the study are to generate accident progression data for the Level II/III PRA source term model and to identify changes that could improve plant response under accident conditions. The scope of the analysis is comprehensive, excluding only sabotage and operator errors of commission. State-of-the-art methodology is employed based largely on the methods developed by Sandia for the US Nuclear Regulatory Commission in support of the NUREG-1150 study. The accident progression model allows complex interactions and dependencies between systems to be explicitly considered. Latin Hypecube sampling was used to assess the phenomenological and systemic uncertainties associated with the primary and confinement system responses to the core damage accident. The results of the analysis show that the N Reactor confinement concept provides significant radiological protection for most of the accident progression pathways studied.

It is worth considering an experiment on a sum resonance. I will give an analytic treatment of a third-order sum resonance. The treatment parallels that in LS-132 for the Walkinshaw difference resonance. Although the algebra is essentially the same as for the difference resonance, the sum resonance appears to have a richer structure.

The Bonneville Power Administration (BPA) initiated the Residential Standards Demonstration Program (RSDP) in 1983 to determine the costs and thermal performance improvements associated with increased levels of thermal integrity in new residences, as proposed by the Northwest Power Planning Council in the Model Conservation Standards (MCS). The program resulted in the construction of approximately 430 new residences, built to thermal performance standards, as dictated by the MCS in each of three climate zones in the region. A subset of the residences has been included in the End-Use Load and Consumer Assessment Program (ELCAP) being conducted by the Pacific Northwest Laboratory (PNL) for the Bonneville Power Administration (BPA). These structures are metered to record hourly energy consumption for several end-uses. Many of the structures built to the MCS include air-to-air heat exchangers (AAHXs) to provide ventilation for maintenance of indoor air quality and comfort. Of the 71 MCS structures included in the ELCAP sample, 38 included air-to-air heat exchangers and had sufficient data to allow an analysis of both use patterns and thermal performance. This report describes the results of the analysis of the AAHX installations using the data collected as part of ELCAP.

The purpose of this report is to fully assess the heating fuel crisis from a broader and longer-term perspective. Using EIA final, monthly data, in conjunction with credible information from non-government sources, the pricing phenomena exhibited by heating fuels in late December 1989 and early January 1990 are described and evaluated in more detail and more accurately than in the interim report. Additionally, data through February 1990 (and, in some cases, preliminary figures for March) make it possible to assess the market impact of movements in prices and supplies over the heating season as a whole. Finally, the longer time frame and the availability of quarterly reports filed with the Securities and Exchange Commission make it possible to weigh the impact of revenue gains in December and January on overall profits over the two winter quarters. Some of the major, related issues raised during the House and Senate hearings in January concerned the structure of heating fuel markets and the degree to which changes in this structure over the last decade may have influenced the behavior and financial performance of market participants. Have these markets become more concentrated Was collusion or market manipulation behind December's rising prices Did these, or …

Until 1988, solutions containing sodium hydroxide, nitride acid, low levels of radionuclides (mostly tritiated water) and some metals were discharged to unlined seepage basins at the F and H Areas of the Savannah River Site (SRS) as part of normal operations (Killian et al, 1987a,b). The basins are now being closed according to the Resource Conservation and Recovery Act (RCRA). As part of the closure, a Part B Post-Closure Care Permit is being prepared. The information included in this report will fulfill some of the data requirements for that Part B permit. Several soil and water samples were collected along the Four Mile Creek (FMC) seepline at the F H Areas of the Savannah River Site. The samples were analyzed for concentrations of metals, radionuclides, and inorganic constituents. The goal of the work reported herein is to document the impacts from the basins of FMC has been completed in a phased approach.

Several soil and water samples were collected along the Four Mile Creek (FMC) seepline at the F H Areas of the Savannah River Site. The samples were analyzed for concentrations of metals, radionuclides, and inorganic constituents. The results of the analyses are summarized below for the soil and water samples.

Until 1988, solutions containing sodium hydroxide, nitride acid, low levels of radionuclides (mostly tritiated water) and some metals were discharged to unlined seepage basins at the F and H Areas of the Savannah River Site (SRS) as part of normal operations (Killian et al, 1987a,b). The basins are now being closed according to the Resource Conservation and Recovery Act (RCRA). As part of the closure, a Part B Post-Closure Care Permit is being prepared. The information included in this report will fulfill some of the data requirements for that Part B permit. Several soil and water samples were collected along the Four Mile Creek (FMC) seepline at the F & H Areas of the Savannah River Site. The samples were analyzed for concentrations of metals, radionuclides, and inorganic constituents. The goal of the work reported herein is to document the impacts from the basins of FMC has been completed in a phased approach.

Several soil and water samples were collected along the Four Mile Creek (FMC) seepline at the F & H Areas of the Savannah River Site. The samples were analyzed for concentrations of metals, radionuclides, and inorganic constituents. The results of the analyses are summarized below for the soil and water samples.

A report on the determination of density for five endangered sea turtle species in the vicinity of Gulf of Mexico drilling platforms no longer in use and slated for removal using explosives.

In 1990, the Atmospheric and Geophysical Sciences Division begins its 17th year as a division. As the Division has grown over the years, its modeling capabilities have expanded to include a broad range of time and space scales ranging from hours to decades and from local to global. Our modeling is now reaching out from its atmospheric focus to treat linkages with the oceans and the land. In this report, we describe the Division's goal and organizational structure. We also provide tables and appendices describing the Division's budget, personnel, models, and publications. 2 figs., 1 tab.

This report combines six work units performed in FY`85--86 by the Copper Development Association and the International Copper Research Association under contract with the University of California. The work includes literature surveys and state-of-the-art summaries on several considerations influencing the feasibility of the use of copper-base materials for fabricating high-level nuclear waste packages for the proposed repository in tuff rock at Yucca Mountain, Nevada. The general conclusion from this work was that copper-base materials are viable candidates for inclusion in the materials selection process for this application. 55 refs., 48 figs., 22 tabs.

Version 16.2 of the FLOWTRAN code with a Savannah River Site (SRS) working criterion (St=0.00455) for the onset of significant void (OSV) was benchmarked against power and flow excursion data derived from tests at the Babcock Wilcox Alliance Research Center test facility. This document presents analyses which show that FLOWTRAN accurately predicts the mockup test assembly thermal-hydraulic behavior during the steady state and LOCA transient conditions, and that FLOWTRAN with a Savannah River Site (SRS) working limits criterion (St=0.00455) conservatively predicts the OFI power.

Version 16.2 of the FLOWTRAN code with a Savannah River Site (SRS) working criterion (St=0.00455) for the onset of significant void (OSV) was benchmarked against power and flow excursion data derived from tests at the Babcock & Wilcox Alliance Research Center test facility. This document presents analyses which show that FLOWTRAN accurately predicts the mockup test assembly thermal-hydraulic behavior during the steady state and LOCA transient conditions, and that FLOWTRAN with a Savannah River Site (SRS) working limits criterion (St=0.00455) conservatively predicts the OFI power.

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This report discusses the following topics in relation to the Bevalac accelerator: accelerator technology operations summary; nuclear science; biomedical research; and publications and presentations.

A report on High Definition Television (HDTV. During 1989, HDTV moved from obscurity to center stage in the ongoing debate over the role of the Federal Government in U.S. industrial competitiveness. HDTV and related High-Resolution System (HRS) technologies in the computer and communications sectors may significantly impact U.S. electronics manufacturing, accelerate fundamental restructuring of the U.S. communications infrastructure, and provide a host of valuable services.

Newly developed bulk-boronized graphites and boronized C-C composites with a total boron concentration ranging from 1 wt % to 30 wt % have been evaluated as plasma-facing component materials for the International Thermonuclear Experimental Reactor (ITER). Bulk-boronized graphites have been bombarded with high-flux deuterium plasmas at temperatures between 200 and 1600{degree}C. Plasma interaction induced erosion of bulk-boronized graphites is observed to be a factor of 2--3 smaller than that of pyrolytic graphite, in regimes of physical sputtering, chemical sputtering and radiation enhanced sublimation. Postbombardment thermal desorption spectroscopy indicates that bulk-boronized graphites enhance recombinative desorption of deuterium, which leads to a suppression of the formation of deuterocarbon due to chemical sputtering. The tritium inventory in graphite has been found to decrease by an order of magnitude due to 10 wt % bulk-boronization at temperatures above 1000{degree}C. The critical heat flux to induce cracking for bulk-boronized graphites has been found to be essentially the same as that for non-boronized graphites. Also, 10 wt % bulk-boronization of graphite hinders air oxidation nearly completely at 800{degree}C and reduces the steam oxidation rate by a factor of 2--3 at around 1100 and 1350{degree}C. 38 refs., 5 figs.

The release of {sup 14}C as {sup 14}CO{sub 2} from partly failed spent fuel containers has been analyzed by the flow of gases into and out of the containers. This flow of gases is driven by pressure differences, which are in turn caused by heating by the spent fuel. In this analysis, the timing and size of holes in the containers are assumed to be given. A better means of predicting the time distribution and sizes of penetrations in nuclear waste containers is needed. For the purposes of far-field transport calculations, we have adopted release rates that are shown to be bonding for the large range of hole sizes studied. The transport of released {sup 14}CO{sub 2} has been analyzed by transport in equivalent porous medium. The peak {sup 14}CO{sub 2} concentration in pore gas at 350 m above the repository does not depend on the time of hole occurrence, although the time of penetration obviously affects the arrival and duration of exposure to {sup 14}C. Nor does water saturation have much effect on peak concentration. In this analysis we have used a constant gas Darcy velocity. We performed limited sensitivity analysis on gas Darcy velocity by using values one …

Populations of wild salmon and steelhead in the Middle Fork of the Salmon River are at historical lows. Until passage and flow problems associated with Columbia River dams are corrected to reduce mortalities of migrating smolts, continuance of habitat enhancements that decrease sediment loads, increase vegetative cover, remove passage barriers, and provide habitat diversity is imperative to maintain surviving populations of these specially adapted fish. In 1987-1988, 4.3 miles of fence was constructed establishing a riparian livestock exclosure. One end-gap and two water-crossing corridors were constructed in 1989 to complete the fence system. Areas within the exclosure have been fertilized to promote tree and shrub root growth and meadow recovery. A stream crossing ford was stabilized with angular cobble. Streambank stabilization/habitat cover work was completed at three sites and three additional habitat structures were placed. Extensive inventories were completed to identify habitat available to anadromous fish. Streambank stabilization work was limited to extremely unstable banks, minimizing radical alterations to an active stream channel. Enhancement activities will improve spawning, incubation, and rearing habitat for wild populations of steelhead trout and chinook salmon. Anadromous species population increases resulting from these enhancement activities will provide partial compensation for downstream losses resulting from hydroelectric …

A report on cash equivalence analysis and seller financing.

We describe a numerical technique for solving two-dimensional, compressible, multimaterial problems using a general topology mesh. Multimaterial problems are characterized by the presence of interfaces whose shapes may become arbitrarily complex in the course of dynamic evolution. Computational methods based on more conventional fixed-connectivity quadrilateral meshes do not have adequate flexibility to follow convoluted interface shapes and frequently fail due to excessive mesh distortion. The present method is based on a mesh of arbitrary polygonal cells. Because this mesh is dual to a triangulation, its topology is unrestricted and it is able to accommodate arbitrary boundary shapes. Additionally, this mesh is able to quickly and smoothly change local mesh resolution, thus economizing on the number of mesh cells, and it is able to improve mesh isotropy because in a region of uniform mesh the cells tend to become regular hexagons. The underlying algorithms are based on those of the CAVEAT code. These consist of an explicit, finite-volume, cell-centered, arbitrary Lagrangian-Eulerian technique, coupled with the Godunov method, which together are readily adaptable to a general topology mesh. Several special techniques have been developed for this extension to a more general mesh. They include an interface propagation scheme based on Huygens' construction, …