The Northwest Power Planning Council convened a symposium in Olympia, Washington, on the subject of global climate change ( the greenhouse effect'') and its potential for affecting the Pacific Northwest. The symposium was organized in response to a need by the Power Council to understand global climate change and its potential impacts on resource planning and fish and wildlife planning for the region, as well as a need to understand national policy developing toward climate change and the Pacific Northwest's role in it. 40 figs., 15 tabs.

In 1984 Argonne National Laboratory (ANL) began an aggressive program of research and development based on the concept of a closed system for fast-reactor power generation and on-site fuel reprocessing, exclusively designed around the use of metallic fuel. This is the Integral Fast Reactor (IFR). Although the Experimental Breeder Reactor-II (EBR-II) has used metallic fuel since its creation 25 yeas ago, in 1985 ANL began a study of the characteristics and behavior of an advanced-design metallic fuel based on uranium-zirconium (U-Zr) and uranium-plutonium-zirconium (U-Pu-Zr) alloys. During the past five years several areas were addressed concerning the performance of this fuel system. In all instances of testing the metallic fuel has demonstrated its ability to perform reliably to high burnups under varying design conditions. This paper will present one area of testing which concerns the fuel system's performance under breach conditions. It is the purpose of this paper to document the observed post-breach behavior of this advanced-design metallic fuel. 2 figs., 1 tab.

During pilot scale operations of the Scale Glass Melter for the US Department of Energy a team of engineers and scientists was formed to assess the need for continued melter design development to support the Defense Waste Processing Facility (DWPF), and prioritize future efforts. Recently this has taken on new importance because of selection of the DWPF Melter design as the reference for the Hanford Waste Vitrification Project (HWVP), and increased interest at the West Valley Demonstration Project on melter life and replacement. Results of the study are summarized, and goals produced by the study are compared to the results of current programs at the Savannah River Laboratory (SRL).

We built a multimedia document system for the SIGGRAPH Interactive Proceedings to demonstrate the potentials and challenges in using technology to capture better the essence of SIGGRAPH conferences. The prototype system uses the NeXT computer system to present textual, mathematical, illustrative, colorful, audio, video and animated material. Special attention was given to including tools for interactive manipulation of images included in typical SIGGRAPH papers. 6 refs., 6 figs.

It is shown that LEP probes the Big Bang in two significant ways: (1) nucleosynthesis and (2) dark matter constraints. In the first case, LEP verifies the cosmological standard model prediction on the number of neutrino types, thus strengthening the conclusion that the cosmological baryon density is {approximately}6% of the critical value. In the second case, LEP shows that the remaining non-baryonic cosmological matter must be somewhat more massive and/or more weakly interacting that the favorite non-baryonic dark matter candidates of a few years ago. 59 refs., 4 figs., 2 tabs.

Thermal radiation plays a key role in the operation and efficiency of combustion systems, accounting for over 90% of the heat transfer. The analysis of radiative heat transfer in coal-fired boilers, combustion chambers and other energy systems requires accounting for the effects of inorganic deposits on bounding surfaces and of entrained particulates, such as pulverized coal, char, and fly-ash. These effects can be predicted; however, the accuracy in predicting the radiative properties of entrained pyrolysis (ash) and deposit layers (slag) is limited by inaccurate knowledge of the physical/chemical properties of the materials over a range of material temperatures and radiative wavelengths that is representative of conditions in practical combustion systems. The objective of this project is to make laboratory measurements of the radiative properties of extracted ash and slag deposit samples.

We propose that most pores in coals are closed. They cannot be reached by diffusion through a pore network but can only be reached by diffusion through solid coal. Co{sub 2} gives accurate total surface areas because it dissolves in and rapidly diffuses through solid coals, reaching all the pores. This surface area is irrelevant to materials which are only slightly soluble or insoluble in coals for these can only reach a small portion of the pores. Thus, the diffusion rate controls the determined pore size. For the large molecules involved in direct-liquefaction and most organic reactions, the effective surface areas of these coals are very small, only a few m{sup 2}/g. The consequences of this structure model for coal processing and reaction are significant. These coals cannot be considered high (hundreds of m{sup 2}/g) surface area materials which are easily accessible. They are low surface area solids only slightly permeable to hydrocarbons. The advantages of fine grinding are obvious. Using solvents which will cause coal to become rubbery rather than glassy will enhance diffusion and thus reactivity.

Solar flares and magnetospheric substorms are each presumably processes by which energy is released from storage in magnetic fields and converted into kinetic energy of plasma and energetic particles. There are a number of analogies between flares and substorms. This paper briefly discusses substorms, their expansion and recovery phases, and a model by which they are presently explained. Two features of substorms, the retreating neutral line'' and the separatrix layer'' are offered as features which might have identifiable (observable ) analogies in flares. 13 refs., 11 figs.

Seven proposed criteria for demonstration of success in waste reduction have been developed: reduced amount of hazardous waste, reduced waste management cost, improved regulatory compliance, reduced health risk, increased production efficiency, reduced accident risk, and improved public relations. A detailed description of each of the criteria is presented along with a discussion for each of the mechanisms for measurement, required commitments, strengths, and weaknesses. 2 refs.

The Commission published a Notice of Proposed Rule-making on Maintenance of Nuclear Power Plants on November 28, 1988, spelling out NRC's expectations in maintenance. In preparing the proposed rule, the NRC reviewed maintenance practices in other countries and considered maintenance approaches in other industries in this country. As a result of the review of maintenance practices, it was concluded that certain practices in the following areas have been found to contribute significantly to effective maintenance: (1) systems approach; (2) effectiveness monitoring; (3) technician qualifications and motivation; and (4) maintenance organization. 87 refs., 26 figs., 2 tabs.

The Graph Structure (GRPHSTRUC) Model is a software system tool specifically developed to be used by a computer security analyst to study the security and analyze the design of computer networks. However, any system that can be characterized and represented by a graph structure could employ GRPHSTRUC with some minor system modifications. The GRPHSTRUC model is a knowledge-based expert system using icons and object-oriented programming methodologies. GRPHSTRUC has been designed and developed to use classical graph theory and allow the display of components and links of a graph structure. A graph G = (V,E) is a structure that consists of a finite set of vertices V and a finite set of edges E. A computer network is a graph structure; the vertices are the components of the network and the edges are the links between components. The GRPHSTRUC model provides a user interface that is designed to give a user the ability to rapidly and efficiently represent graph components, connections, and relationships. 9 refs., 1 fig.

Explicit integral expressions are given for the fifth-order geometrical aberration coefficients in rectilinear magnetic quadrupole-octupole systems used for the transport of nonrelativistic charged particle beams. The numerical values of the fifth-order geometrical aberration coefficients for a rare earth cobalt (REC) quadrupole doublet are given as an example. 26 refs., 5 figs., 4 tabs.

Perimeter radiation monitors are gamma-ray and neutron measurement systems that can provide timely notice of theft or diversion of special nuclear material (SNM). The monitors may be hand-held instruments operated by security inspectors or automatic pedestrian or vehicle monitors located in exit pathways. A monitor's performance depends on its design, the characteristics of SNM and the operating environment, and proper monitor calibration and maintenance. Goals of ASTM Subcommittee C26.12 are to describe monitoring technology, how to apply it, and how to test its performance. 3 refs., 6 figs.

The CDF detector has collected data for an integrated luminosity of 4.4 pb{sup {minus}1} during the 1988--89 Tevatron Collider run. This sample has been used to search for the top quark. We report here the results of the analysis of the electron-muon topology. We find that a top mass in the 28 to 72 GeV is excluded at the 95% confidence level. The same limits apply to a possible fourth generation, charge {minus}1/3, b{prime} quark decaying via the charged current. 21 refs., 14 figs.

The objectives of this contract are to develop a technology for the production of active and stable iron Fischer-Tropsch catalysts for use in slurry-phase synthesis reactors and to develop a scale-up procedure for large-scale synthesis of such catalysts for process development and long-term testing in slurry bubble column reactors. With a feed containing H{sub 2}:CO in the ratio of 0.5 to 1.0, the catalyst performance target in the slurry bubble column reactor is 88% CO + H{sub 2}conversion at a minimum space velocity of 2.4 NL/h/gFe. The methane + ethane selectivity is desired to be no more than 4% and the conversion loss per week is not to exceed 1%.

In FY 1987, a program was initiated to demonstrate technology for recovering transuranic (TRU) elements from defense wastes. This hot demonstration was to be carried out with solution from the dissolution of irradiated fuels. This recovery would be accomplished with both PUREX and TRUEX solvent extraction processes. Work planned for this program included preparation of a shielded-cell facility for the receipt and storage of spent fuel from commercial power reactors, dissolution of this fuel, operation of a PUREX process to produce specific feeds for the TRUEX process, operation of a TRUEX process to remove residual actinide elements from PUREX process raffinates, and processing and disposal of waste and product streams. This report documents the work completed in planning and starting up this program. It is meant to serve as a guide for anyone planning similar demonstrations of TRUEX or other solvent extraction processing in a shielded-cell facility.

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.

In the first part of this paper, a reevaluation of the low-energy neutron cross sections of {sup 235}U is described. This reevaluation was motivated by the discrepancy between the measured and computed temperature coefficients of reactivity and is based on recent measurements of the fission cross section and of {eta} in the thermal and subthermal neutron energy regions. In the second part of the paper, we discuss the conversion of the Reich-Moore resonance parameters, describing the neutron cross sections of {sup 235}U in the resolved resonance region, into equivalent Adler-Adler resonance parameters and into equivalent momentum space multipole resonance parameters. 25 refs., 4 figs., 5 tabs.

The Impression Creep technique has been applied to XD{trademark} TiAl weldments to evaluate the local creep resistance of the fusion zone and the heat affected zone. The material used in this study was TiAl produced by Martin Marietta Research Laboratories, using their patented ingot processing which incorporates 1 to 10 {mu}m diameter particles of carbide, nitride or boride compounds. The impression creep technique uses a small indenter to locally evaluate the creep resistance of the heterogeneous microstructure developed during the welding process. The indenters used in this investigation were 1 mm in diameter. Results obtained from the impression creep tests are compared to results obtained from constant stress tensile creep tests on the base material. Creep resistance of the heat affected zone and the fusion zone are compared to and contrasted with the base material strength. 19 refs., 2 figs., 2 tabs.

The collimators at Sector 30 of the SLAC accelerator are designed to scrape off a significant fraction (e.g., {approximately}20%) of the SLC beam. The electromagnetic cascade shower that develops in the collimator, and in the scraper and waveguide downbeam, leads to very high radiation exposures of TV cameras (and other devices) located nearby. The collimator (point) source accounts for one-third of the dose and is best shielded by extending the radius of the copper scraper. Radiation from the waveguide accounts for the remaining two-thirds of the dose, and is difficult to shield since it is a line source. However, the spectrum from the waveguide is expected to be softer than that from the collimator. This paper discusses shielding of these sources.

The Savannah River Site has many operating years of experience with various facilities. Fires have occurred throughout the years at many of these facilities, but in general with only minor consequences. There has never been a fire related loss of life or serious injury on site. The maximum dollar loss of a single fire was approximately $400,000 involving a coal and oil fire in D area. the following is a synopsis of data included in the fire division Industrial Fire records from January of 1958 until November of 1989. It includes fires from all areas on site which were attended by or reported to the fire division. The fires are characterized by number of occurrences, site areas and buildings in which they occurred, dollar losses sustained, the cause of the fire, and what type of suppression method was used to extinguish the fire. The reactor areas are included in all discussions of site wide fires, but are also singled out and analyzed separately due to perceived significance of fires there. Discussion of the completeness of the Industrial Fire data base is also included. 29 figs., 3 tabs.

This report summarizes the results of eight crucible melt tests and three bench-scale in situ vitrification (ISV) test that were performed on simulated metals/soils mixtures containing actual site soils from the Idaho National Engineering Laboratory (INEL). The crucible melt and bench-scale ISV tests are a part of efforts by the Pacific Northwest Laboratory (PNL) to assist the INEL in conducting a treatability study on ISV for application to the mixed waste buried at the INEL subsurface disposal area (SDA). The crucible melt tests were performed to evaluate the effect of various chemical additives and metal oxidation techniques on soil melting temperatures, melt viscosities, metals versus electrode oxidation potentials, and metals incorporation in the glass. The bench-scale ISV tests were performed to supplement the existing ISV data base with information on certain hazardous materials that have not been adequately evaluated in previous ISV tests. These materials included five EP toxicity metals, various volatile organic materials fixed in a cementitious matrix (including carbon tetrachloride (CCl{sub 4}), trichloroethylene (TCE), and tetrachloroethylene (PCE)), and asbestos. In addition, the bench-scale test were used to evaluated the effect of the proposed chemical additive on ISV processing performance and product quality. 8 refs., 24 figs., 19 tabs.

Two methods have been developed for the computation of resonance integrals in cells containing annular fuel regions. Both are based on rational approximations. One is a generalization of a one-term rational approximation method developed by Segev for a cell with a single fuel annulus. The second modifies the earlier Chen-Gelbard two-term method originally used for double-heterogeneity calculations. Both methods were tested, in cells with two fuel annuli, for various U{sup 235} and U{sup 238} resonances. Both gives resonance integrals accurate enough for practical purposes. The two-term fits are substantially more accurate in some NR cases, but are somewhat more difficult to correct for finite resonance widths. 8 refs., 4 tabs.

The purpose of this work was fivefold: to develop an expanded neutron cross-section library containing approximately 1200 cross-section sets with the Hansen-Roach (H-R) sixteen neutron-energy-group structure; to provide an enhanced computational tool on a personal computer for criticality calculations; to provide consistent values of the effective scattering cross sections (sigma-s) for each set of the expanded H-R library, for selecting the resonance self-shielded cross sections (sigma-p); to develop a consistent technique for calculating sigma-p to select and apply specific self-shielded cross-section sets; and to apply the cross sections and the selection technique to a wide variety of criticality calculational benchmarks. 18 refs., 1 fig.