In a market economy demands for commodities are met through various technologies and resources. Markets select the technologies and resources to meet these demands based on their costs. Over time, the competitiveness of different technologies can change due to the exhaustion of resources they depend on, the introduction of newer, more efficient technologies, or even shifts in user demands. As this happens, the structure of the economy changes. The Market Equilibrium and Technology Assessment Network Modelling System, META{center_dot}Net, has been developed for building and solving multi-period equilibrium models to analyze the shifts in the energy system that may occur as new technologies are introduced and resources are exhausted. META{center_dot}Net allows a user to build and solve complex economic models. It models` a market economy as a network of nodes representing resources, conversion processes, markets, and end-use demands. Commodities flow through this network from resources, through conversion processes and market, to the end-users. META{center_dot}Net then finds the multiperiod equilibrium prices and quantities. The solution includes the prices and quantities demanded for each commodity along with the capacity additions (and retirements) for each conversion process, and the trajectories of resource extraction. Although the changes in the economy are largely driven by consumers` …

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Two different methods will be used to affix ladders to the active bulkhead. Layer 1 and layer 3 ladders will be attached to the active bulkhead using pins. To provide a highly conductive thermal path between these ladders and the cooling channel in the active bulkhead, a small amount of thermally conductive grease will be applied to the bulkhead just prior to ladder installation. Layer 2 and layer 4 ladders will be attached using the same method with the exception that thermally conductive epoxy will be used in lieu of grease. The epoxy is necessary in the outer two layers to maintain barrel rigidity. One major point of concern is the removal of the epoxied ladders. If removal of one of these ladders becomes necessary, it is unclear if the epoxy bond can be broken without damaging the silicon. This report is an attempt to estimate the amount of force necessary to remove a ladder, and the resulting stress that force produces in the silicon. The force necessary to remove an epoxied ladder from a bulkhead is calculated. The resulting silicon stress is also calculated.

During the last few years, there has been an increased effort to devise robust transport differencings for unstructured meshes, specifically arbitrarily connected grids of polygons. Adams has investigated unstructured mesh discretization techniques for the even- and odd-parity forms of the transport equation, and for the more traditional first-order form. Conversely, development of unstructured mesh diffusion methods has been lacking. While Morel, Kershaw, Shestakov and others have done a great deal of work on diffusion schemes for logically-rectangular grids, to the author`s knowledge there has been no work on discretizations of the diffusion equation on unstructured meshes of polygons. In this paper, the authors introduce a point-centered diffusion differencing for two-dimensional unstructured meshes. They have designed the method to have the following attractive properties: (1) the scheme is equivalent to the standard five-point point-centered scheme on an orthogonal mesh; (2) the method preserves the homogeneous linear solution; (3) the method gives second-order accuracy; (4) they have strict conservation within the control volume surrounding each point; and (5) the numerical solution converges to the exact result as the mesh is refined, regardless of the smoothness of the mesh. A potential disadvantage of the method is that the diffusion matrix is asymmetric, in …

This document establishes the technical basis in support of Emergency Planning Activities for the Fast Flux Test Facility on the Hanford Site. The document represents an acceptable interpretation of the implementing guidance document for DOE Order 5500.3A. Through this document, the technical basis for the development of facility specific Emergency Action Levels and the Emergency Planning Zone is demonstrated.

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This Source Guide will assist those working with the National Environmental Policy Act of 1969 (NEPA) to become more familiar with the Environmental Assessments (EA) and Environmental Impact Statements (EIS) that apply to specific activities and facilities at the Hanford Site. This document should help answer questions concerning NEPA coverage, history, processes, and the status of many of the buildings and units on and related to the Hanford Site. This document summarizes relevant EAs and EISs by briefly outlining the proposed action of each and the decision made by the US Department of Energy (DOE) or its predecessor agencies, the US Atomic Energy Commission (AEC), and the US Energy Research and Development Administration (ERDA), concerning the proposed action and current status of the buildings and units discussed in the proposed action. If a decision was officially stated by the DOE, as in a finding of no significant impact (FONSI) or a Record of Decision (ROD), and was located, a summary is provided in the text. Not all federal decisions, such as FONSIs and RODS, can be found in the Federal Register (FR). For example, although significant large-action FONSIs can be found in the FR, some low-interest FONSIs may have been …

A multi-faceted study was initiated in November 1993 to provide assurance that needed testing capabilities, facilities, and support infrastructure (sampling systems, casks, transportation systems, permits, etc.) would be available when needed for process and equipment development to support pretreatment and vitrification facility design and construction schedules. This first major report provides a snapshot of the known testing needs for pretreatment, low-level waste (LLW) and high-level waste (HLW) vitrification, and documents the results of a series of preliminary studies and workshops to define the issues needing resolution by cold or hot testing. Identified in this report are more than 140 Hanford Site tank waste pretreatment and LLW/HLW vitrification technology issues that can only be resolved by testing. The report also broadly characterizes the level of testing needed to resolve each issue. A second report will provide a strategy(ies) for ensuring timely test capability. Later reports will assess the capabilities of existing facilities to support needed testing and will recommend siting of the tests together with needed facility and infrastructure upgrades or additions.

The purpose of note No. 60 is to outline the reasons why it is important to develop and test a steam ejector for use on the differential pumping station. Note No. 79 discusses two stream instability of an electron beam in the differential pumped transport section. Note No. 116 covers the steam ejector prototype unit (Stage 1). And lastly, note No. 136 presents the results of a survey done to find the commercially available equipment to meet differential pump requirements for the Advanced Test Accelerator.

The authors consider the following problem that arises in assembly planning: given an assembly, identify a subassembly that can be removed as a rigid object without disturbing the rest of the assembly. This is the assembly partitioning problem. Specifically, they consider planar assemblies of simple polygons and subassembly removal paths consisting of a single finite translation followed by a translation to infinity. They show that such a subassembly and removal path can be determined in O(n{sup 1.46}N{sup 6}) time, where n is the number of polygons in the assembly and N is the total number of edges and vertices of all the parts together. They then extend this formulation to removal paths consisting of a small number of finite translations, followed by a translation to infinity. In this case the algorithm runs in time polynomial in the number of parts, but exponential in the number of translations a path may contain.

This document provides descriptions of components and tasks that are involved in the computer system for the data acquisition and control of the mitigation tests conducted on waste tank SY-101 at the Hanford Nuclear Reservation. The system was designed and implemented by Los alamos National Laboratory and supplied to Westinghouse Hanford Company. The computers (both personal computers and specialized data-taking computers) and the software programs of the system will hereafter collectively be referred to as the DACS (Data Acquisition and Control System).

This report discusses the Convention on International Trade in Endangered Species of Wild Fauna and Flora (CITES). It is divided into six sections: Introduction, Background, CITES and the Endangered Species Act, Implementation, Upcoming Events, and Appendices.

The Electric Power Monthly (EPM) presents monthly electricity statistics. The purpose of this publication is to provide energy decisionmakers with accurate and timely information that may be used in forming various perspectives on electric issues that lie ahead. Data in this report are presented for a wide audience including Congress, Federal and State agencies, the electric utility industry, and the general public. The EIA collected the information in this report to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275) as amended.

This report evaluates the impacts assessment and proposed mitigations provided in environmental documents concerning the US Department of Energy`s (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The projected impacts and proposed mitigations identified in UMTRA Project environmental documents were evaluated for two UMTRA Project sites. These sites are Gunnison and Durango, which are representative of currently active and inactive UMTRA Project sites, respectively. National Environmental Policy Act (NEPA) documentation was prepared for the remedial action at Durango and Gunnison as well as for the provision of an alternate water supply system at Gunnison. Additionally, environmental analysis was completed for mill site demolition Gunnison, and for a new road related to the Durango remedial action. The results in this report pertain only to the impact assessments prepared by the Regulatory Compliance staff as a part of the NEPA compliance requirements. Similarly, the mitigative measures documented are those that were identified during the NEPA process.

The design considerations for a long-range Purkinje effects based video tracking system using current technology is presented. Past work, current experiments, and future directions are thoroughly discussed, with an emphasis on digital signal processing techniques and obstacles. It has been determined that while a robust, efficient, long-range, and non-invasive eye tracking system will be difficult to develop, such as a project is indeed feasible.

The Natural Gas Monthly (NGM) highlights activities, events, and analyses of interest to public and private sector organizations associated with the natural gas industry. Volume and price data are presented each month for natural gas production, distribution, consumption, and interstate pipeline activities. Producer-related activities and underground storage data are also reported. From time to time, the NGM features articles designed to assist readers in using and interpreting natural gas information.

The Quarterly Coal Report (QCR) provides comprehensive information about US coal production, distribution, exports, imports, receipts, prices, consumption, and stocks to a wide audience, including Congress, Federal and State agencies, the coal industry, and the general public. Coke production, consumption, distribution, imports, and exports data are also provided. The data presented in the QCR are collected and published by the Energy Information Administration (EIA) to fulfill data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275), as amended. This report presents detailed quarterly data for January through March 1994 and aggregated quarterly historical data for 1986 through the fourth quarter of 1993. Appendix A displays, from 1986 on, detailed quarterly historical coal imports data, as specified in Section 202 of the Energy Policy and Conservation Amendments Act of 1985 (Public Law 99-58). Appendix B gives selected quarterly tables converted to metric tons.

A video camera is planned to be installed on the radioactive storage tank 241AW101 at the DOE` s Hanford Site in Richland, Washington. The camera will occupy the 20 inch port of the Multiport Flange riser which is to be installed on riser 5B of the 241AW101 (3,5,10). The objective of the project reported herein was to perform a seismic analysis and evaluation of the structural components of the camera for a postulated Design Basis Earthquake (DBE) per the reference Structural Design Specification (SDS) document (6). The detail of supporting engineering calculations is documented in URS/Blume Calculation No. 66481-01-CA-03 (1).

This document describes the hardware subsystems of the data acquisition and control system (DACS) used in mitigation tests conducted on waste tank SY-101 at the Hanford Nuclear Reservation. The system was designed and implemented by Los Alamos National Laboratory (LANL) and supplied to Westinghouse Hanford Company (WHC). The mitigation testing uses a pump immersed in the waste tank, directed at certain angles and operated at different speeds and time durations. The SY-101 tank has experienced recurrent periodic gas releases of hydrogen, nitrous oxide, ammonia, and (recently discovered) methane. The hydrogen gas represents a danger, as some of the releases are in amounts above the lower flammability limit (LFL). These large gas releases must be mitigated. Several instruments have been added to the tank to monitor the gas compositions, the tank level, the tank temperature, and other parameters. A mixer pump has been developed to stir the tank waste to cause the gases to be released at a slow rate. It is the function of the DACS to monitor those instruments and to control the mixer pump in a safe manner. During FY93 and FY94 the mixer pump was installed with associated testing operations support equipment and a mitigation test project …

The purpose of this test plan is to demonstrate the synthesis of inorganic antimonate ion exchangers and compare their performance against the standard organic cation exchangers. Of particular interest is the degradation rate of both inorganic and organic cation exchangers. This degradation rate will be tracked by determining the ion exchange capacity and thermal stability as a function of time, radiation dose, and chemical reaction.

Goal was to use NMR to study TBP/lanthanide complexes in the interlayer or on edge sites of clays. Work in this laboratory yielded details of the complexation of Eu(NO{sub 3}){sub 3} and Pr(NO{sub 3}){sub 3} with TBP in hexane solution; this information is crucial to interpretation of results of NMR studies of the complexes exchanged into clays. The solution {sup 31}P-chemical shift values were improved by repeating the studies on the lanthanide salts dissolved directly into neat TBP. NMR studies of these neat solutions of the Eu(NO{sub 3}){sub 3}{lg_bullet}3TBP-complex and the Pr(NO{sub 3}){sub 3}{lg_bullet}3TBP-complex show that the {sup 31}P chemical shift remains relatively constant for TBP: lanthanide ratios below 3: 1. At higher ratios, the chemical shift approaches that of free TBP, indicating rapid exchange of TBP between the free and complexed state. Exchange of these complexes into the clay hectorite yielded discrete {sup 31}P-NMR signals for the Eu{lg_bullet}TBP complex at -190 ppm and free TBP at -6 ppm. Adsorption of the Pr{lg_bullet}TBP complex yielded broad signals at 76 ppm for the complex and -6 ppm for free TBP. There was no evidence of exchange between the incorporated complex and the free TBP.

The following aquifer testing data supported 1993 Interim Remedial Measure field work for the U-1 and U-2 crib area near the uranium technetium and nitrate plumes beneath the U Plant Aggregate Area. The purpose of aquifer testing was to fill in hydraulic conductivity data gaps in the western portion of 200 West Area and help refine the hydrogeologic conceptual model. This data package reports data collected in accordance with the description of work released in 1993 by L.C. Swanson, entitled Description of Work for the 200-UP-1 Aquifer Testing Activity. These data are analyzed in the document Aquifer Test Analysis Results for 1993 200-UP-1 Groundwater Operable Unit. Slug tests were conducted at 7 existing wells, and pumping tests were conducted at 2 of those same existing wells.

CHEETAH is an effort to bring the TIGER thermochemical code into the 1990s. A wide variety of improvements have been made in Version 1.0, and a host of others will be implemented in the future. In CHEETAH 1.0 I have improved the robustness and ease of use of TIGER. All of TIGER`s solvers have been replaced by new algorithms. I find that CHEETAH solves a wider variety of problems with no user intervention (e.g. no guesses for the C-J state) than TIGER did. CHEETAH has been made simpler to use than TIGER; typical use of the code occurs with the new standard run command. I hope that CHEETAH makes the use of thermochemical codes more attractive to practical explosive formulators. In the future I plan to improve the underlying science in CHEETAH. More accurate equations of state will be used in the gas and the condensed phase. A kinetics capability will be added to the code that will predict reaction zone thickness. CHEETAH is currently a numerical implementation of C-J theory. It will,become an implementation of ZND theory. Further ease of use features will eventually be added; an automatic formulator that adjusts concentrations to match desired properties is planned.

The radiological decay heat generated from all irradiated fuel presently in K East (KE) and K West (KW) Basins was calculated in support of consolidated fuel storage. There are four sources of heat inflow into the fuel storage basins: (1) radiological decay heat from irradiated fuel; (2) mechanical heat from operating machinery (e.g., pumps); (3) heat flow from surroundings (mainly the ground through the concrete walls into the basin water if it is maintained below ambient); and (4) exothermic chemical reactions of uranium oxidation (although at basin temperatures this reaction rate is slow). This report details the radiological decay heat from irradiated fuel source in the K basins. Decay heat calculations using ORIGEN2 (Wittekind 1994 and Schmittroth 1993) for irradiated fuel presently (April 1994) in KE and KW Basins gave results for January 31 of each year.