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Sample records for description oecd factbook

  1. CIA-The World Factbook | Open Energy Information

    Open Energy Info (EERE)

    Dataset Website: www.cia.govlibrarypublicationsthe-world-factbookindex.html Cost: Free CIA-The World Factbook Screenshot References: CIA-The World Factbook1 "The World...

  2. Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Description Expert operators from both military and civilian bomb squads and other public safety organizations use advanced skills to maneuver Hazardous Duty Robots in challenging, ...

  3. OECD | OpenEI Community

    Open Energy Info (EERE)

    energy becomes more competitive with fossil fuels in OECD countries, reports of this nature can go a long way to supporting more and more development. The four new reports in...

  4. Organisation for Economic Co-Operation and Development (OECD...

    Open Energy Info (EERE)

    OECD-Private Sector Engagement in Adaptation to Climate Change Visualization of World Energy Supply Add Tool OECD Programs Ethiopia-National Greenhouse Gas Emissions...

  5. Organisation for Economic Co-Operation and Development (OECD...

    Open Energy Info (EERE)

    New Zealand, Norway, Poland, Portugal, Slovakia, Spain, Sweden, Switzerland, Turkey, United Kingdom and United States Mission OECD brings together the governments of...

  6. OECD-Private Sector Engagement in Adaptation to Climate Change...

    Open Energy Info (EERE)

    Private Sector Engagement in Adaptation to Climate Change Jump to: navigation, search Tool Summary LAUNCH TOOL Name: OECD-Private Sector Engagement in Adaptation to Climate Change...

  7. OECD-Fostering Innovation for Green Growth | Open Energy Information

    Open Energy Info (EERE)

    Fostering Innovation for Green Growth Jump to: navigation, search Tool Summary LAUNCH TOOL Name: OECD-Fostering Innovation for Green Growth AgencyCompany Organization:...

  8. Energy use and carbon emissions: Non-OECD countries

    SciTech Connect (OSTI)

    Not Available

    1994-12-01

    This report surveys world energy use and carbon emissions patterns, with particular emphasis on the non-OECD countries. The non OECD is important not only because it currently makes up 84% of world population, but because its energy consumption, carbon emissions, population, and grow domestic product have all been growing faster than OECD`s. This presentation has seven major sections: (1) overview of key trends in non-OECD energy use and carbon emissions since 1970; (2) Comparison and contrasting energy use and carbon emissions for five major non OEDC regions (former Soviet Union and eastern Europe, Pacific Rim including China, Latin America, other Asia; Africa; 3-7) presentation of aggregate and sectoral energy use and carbon emissions data for countries within each of the 5 regions.

  9. Forecasting Crude Oil Spot Price Using OECD Petroleum Inventory Levels

    Reports and Publications (EIA)

    2003-01-01

    This paper presents a short-term monthly forecasting model of West Texas Intermediate crude oil spot price using Organization for Economic Cooperation and Development (OECD) petroleum inventory levels.

  10. Energy Use and Carbon Emissions: Non-OECD Countries

    Reports and Publications (EIA)

    1994-01-01

    Presents world energy use and carbon emissions patterns, with particular emphasis on the non-OECD (Organization for Economic Cooperation and Development) countries (including the current and former centrally planned economies).

  11. OECD-A Green Growth Strategy for Food and Agriculture | Open...

    Open Energy Info (EERE)

    OECD-A Green Growth Strategy for Food and Agriculture Jump to: navigation, search Tool Summary LAUNCH TOOL Name: OECD-A Green Growth Strategy for Food and Agriculture Agency...

  12. Testbed Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Testbed Description Network R&D Overview Experimental Network Testbeds 100G SDN Testbed Testbed Description Testbed Results Proposal Process Terms and Conditions Dark Fiber Testbed...

  13. Program Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Program Description Inspiring girls to recognize their potential and pursue opportunities in science, technology, engineering and mathematics. Through Expanding Your Horizon (EYH) ...

  14. Testbed Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Testbed Description Network R&D Software-Defined Networking (SDN) Experimental Network Testbeds 100G SDN Testbed Testbed Description Proposal Process Terms and Conditions Dark Fiber Testbed Test Circuit Service Testbed Results Current Testbed Research Previous Testbed Research Performance (perfSONAR) Software & Tools Development Data for Researchers Partnerships Publications Workshops Contact Us Technical Assistance: 1 800-33-ESnet (Inside US) 1 800-333-7638 (Inside US) 1 510-486-7600

  15. OECD-A Green Growth Strategy for Energy | Open Energy Information

    Open Energy Info (EERE)

    A Green Growth Strategy for Energy Jump to: navigation, search Tool Summary LAUNCH TOOL Name: OECD-A Green Growth Strategy for Energy AgencyCompany Organization: Organisation for...

  16. Program Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Program Description SAGE, the Summer of Applied Geophysical Experience, is a unique educational program designed to introduce students in geophysics and related fields to "hands on" geophysical exploration and research. The program emphasizes both teaching of field methods and research related to basic science and a variety of applied problems. SAGE is hosted by the National Security Education Center and the Earth and Environmental Sciences Division of the Los Alamos National

  17. Sensitivity Analysis of OECD Benchmark Tests in BISON

    SciTech Connect (OSTI)

    Swiler, Laura Painton; Gamble, Kyle; Schmidt, Rodney C.; Williamson, Richard

    2015-09-01

    This report summarizes a NEAMS (Nuclear Energy Advanced Modeling and Simulation) project focused on sensitivity analysis of a fuels performance benchmark problem. The benchmark problem was defined by the Uncertainty Analysis in Modeling working group of the Nuclear Science Committee, part of the Nuclear Energy Agency of the Organization for Economic Cooperation and Development (OECD ). The benchmark problem involv ed steady - state behavior of a fuel pin in a Pressurized Water Reactor (PWR). The problem was created in the BISON Fuels Performance code. Dakota was used to generate and analyze 300 samples of 17 input parameters defining core boundary conditions, manuf acturing tolerances , and fuel properties. There were 24 responses of interest, including fuel centerline temperatures at a variety of locations and burnup levels, fission gas released, axial elongation of the fuel pin, etc. Pearson and Spearman correlatio n coefficients and Sobol' variance - based indices were used to perform the sensitivity analysis. This report summarizes the process and presents results from this study.

  18. Summary of important results and SCDAP/RELAP5 analysis for OECD LOFT experiment LP-FP-2

    SciTech Connect (OSTI)

    Coryell, E.W.

    1994-04-01

    This report summarizes significant technical findings from the LP-FP-2 Experiment sponsored by the Organization of Economic Cooperation and Development (OECD). It was the second, and final, fission product experiment conducted in the Loss-of-Fluid Test (LOFT) facility at the Idaho National Engineering Laboratory. The overall technical objective of the test was to contribute to the understanding of fuel rod behavior, hydrogen generation, and fission product release, transport, and deposition during a V-sequence accident scenario that resulted in severe core damage. An 11 by 11 test bundle, comprised of 100 prepressurized fuel rods, 11 control rods, and 10 instrumented guide tubes, was surrounded by an insulating shroud and contained in a specially designed central fuel module, that was inserted into the LOFT reactor. The simulated transient was a V-sequence loss-of-coolant accident scenario featuring a pipe break in the low pressure injection system line attached to the hot leg of the LOFT broken loop piping. The transient was terminated by reflood of the reactor vessel when the outer wall shroud temperature reached 1517 K. With sustained fission power and heat from oxidation and metal-water reactions, elevated temperatures resulted in zircaloy melting, fuel liquefaction, material relocation, and the release of hydrogen, aerosols, and fission products. A description and evaluation of the major phenomena, based upon the response of on line instrumentation, analysis of fission product data, postirradiation examination of the fuel bundle, and calculations using the SCDAP/RELAP5 computer code, are presented.

  19. RELAP5-3D results for phase I (Exercise 2) of the OECD/NEA MHTGR-350 MW benchmark

    SciTech Connect (OSTI)

    Strydom, G.; Epiney, A. S.

    2012-07-01

    The coupling of the PHISICS code suite to the thermal hydraulics system code RELAP5-3D has recently been initiated at the Idaho National Laboratory (INL) to provide a fully coupled prismatic Very High Temperature Reactor (VHTR) system modeling capability as part of the NGNP methods development program. The PHISICS code consists of three modules: INSTANT (performing 3D nodal transport core calculations), MRTAU (depletion and decay heat generation) and a perturbation/mixer module. As part of the verification and validation activities, steady state results have been obtained for Exercise 2 of Phase I of the newly-defined OECD/NEA MHTGR-350 MW Benchmark. This exercise requires participants to calculate a steady-state solution for an End of Equilibrium Cycle 350 MW Modular High Temperature Reactor (MHTGR), using the provided geometry, material, and coolant bypass flow description. The paper provides an overview of the MHTGR Benchmark and presents typical steady state results (e.g. solid and gas temperatures, thermal conductivities) for Phase I Exercise 2. Preliminary results are also provided for the early test phase of Exercise 3 using a two-group cross-section library and the Relap5-3D model developed for Exercise 2. (authors)

  20. RELAP5-3D Results for Phase I (Exercise 2) of the OECD/NEA MHTGR-350 MW Benchmark

    SciTech Connect (OSTI)

    Gerhard Strydom

    2012-06-01

    The coupling of the PHISICS code suite to the thermal hydraulics system code RELAP5-3D has recently been initiated at the Idaho National Laboratory (INL) to provide a fully coupled prismatic Very High Temperature Reactor (VHTR) system modeling capability as part of the NGNP methods development program. The PHISICS code consists of three modules: INSTANT (performing 3D nodal transport core calculations), MRTAU (depletion and decay heat generation) and a perturbation/mixer module. As part of the verification and validation activities, steady state results have been obtained for Exercise 2 of Phase I of the newly-defined OECD/NEA MHTGR-350 MW Benchmark. This exercise requires participants to calculate a steady-state solution for an End of Equilibrium Cycle 350 MW Modular High Temperature Reactor (MHTGR), using the provided geometry, material, and coolant bypass flow description. The paper provides an overview of the MHTGR Benchmark and presents typical steady state results (e.g. solid and gas temperatures, thermal conductivities) for Phase I Exercise 2. Preliminary results are also provided for the early test phase of Exercise 3 using a two-group cross-section library and the Relap5-3D model developed for Exercise 2.

  1. OECD MCCI project final report, February 28, 2006.

    SciTech Connect (OSTI)

    Farmer, M. T.; Lomperski, S.; Kilsdonk, D. J.; Aeschlimann, R. W.; Basu, S.

    2011-05-23

    -dimensional. Although the MACE Scoping Test was carried out with a two-dimensional concrete cavity, the interaction was flooded soon after ablation was initiated to investigate debris coolability. Moreover, due to the scoping nature of this test, the apparatus was minimally instrumented and therefore the results are of limited value from the code validation viewpoint. Aside from the MACE program, the COTELS test series also investigated 2-D CCI under flooded cavity conditions. However, the input power density for these tests was quite high relative to the prototypic case. Finally, the BETA test series provided valuable data on 2-D core concrete interaction under dry cavity conditions, but these tests focused on investigating the interaction of the metallic (steel) phase with concrete. Due to these limitations, there is significant uncertainty in the partitioning of energy dissipated for the ablation of concrete in the lateral and axial directions under dry cavity conditions for the case of a core oxide melt. Accurate knowledge of this 'power split' is important in the evaluation of the consequences of an ex-vessel severe accident; e.g., lateral erosion can undermine containment structures, while axial erosion can penetrate the basemat, leading to ground contamination and/or possible containment bypass. As a result of this uncertainty, there are still substantial differences among computer codes in the prediction of 2-D cavity erosion behavior under both wet and dry cavity conditions. Thus, a second key aim of the current program was to provide the necessary data to help resolve these modeling differences. In light of the above issues, the OECD-sponsored Melt Coolability and Concrete Interaction (MCCI) program was initiated at Argonne National Laboratory. The project conducted reactor materials experiments and associated analysis to achieve the following technical objectives: (1) resolve the ex-vessel debris coolability issue through a program that focused on providing both confirmatory

  2. STEP Intern Job Description

    Broader source: Energy.gov [DOE]

    STEP Intern Job Description, from the Tool Kit Framework: Small Town University Energy Program (STEP).

  3. OECD/NEA study on the economics of the long-term operation of nuclear power plants

    SciTech Connect (OSTI)

    Lokhov, A.; Cameron, R.

    2012-07-01

    The OECD Nuclear Energy Agency (NEA) established the Ad hoc expert group on the Economics of Long-term Operation (LTO) of Nuclear Power Plants. The primary aim of this group is to collect and analyse technical and economic data on the upgrade and lifetime extension experience in OECD countries, and to assess the likely applications for future extensions. This paper describes the key elements of the methodology of economic assessment of LTO and initial findings for selected NEA member countries. (authors)

  4. Research Project Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    No job description found Current Research Opportunities Water Quality Standards and Feasibility Studies National Permit Discharge Elimination System Permitting Physiologically...

  5. HAZWOPER Training Program Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    55 Revision 0 Hanford Standardized HAZWOPER Training Program Description Prepared for the U.S. Department of Energy Assistant Secretary for Environmental Management Approved for Public Release; Further Dissemination Unlimited Hanford Standardized HAZWOPER Training Program Description, DOE-0355 Page 2 of 12 Senior Management Team Approval Hanford Standardized HAZWOPER Training Program Description, DOE-0355 Page 3 of 12 Hanford Training Manager Approval Hanford Standardized HAZWOPER Training

  6. TMACS version description document

    SciTech Connect (OSTI)

    GLASSCOCK, J.A.

    1999-05-13

    This document updates the Version Description Document with the changes incorporated in the Revision 11.0 software installation on the Tank Monitor and Control System (TMACS).

  7. Detailed Income Statement Descriptions

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Program Description Sales Sales under the Transmission Rate Schedules Miscellaneous Revenue Sales that are not subject to Transmission rates schedules Inter-Business Unit...

  8. VISION Model: Description

    SciTech Connect (OSTI)

    2009-01-18

    Description of VISION model, which is used to estimate the impact of highway vehicle technologies and fuels on energy use and carbon emissions to 2050.

  9. Summary of comparison and analysis of results from exercises 1 and 2 of the OECD PBMR coupled neutronics/thermal hydraulics transient benchmark

    SciTech Connect (OSTI)

    Mkhabela, P.; Han, J.; Tyobeka, B.; Ivanov, K.; Reitsma, F.; Sartori, E.

    2006-07-01

    The Nuclear Energy Agency (NEA) of the Organization for Economic Cooperation and Development (OECD) has accepted, through the Nuclear Science Committee (NSC), the inclusion of the Pebble-Bed Modular Reactor 400 MW design (PBMR-400) coupled neutronics/thermal hydraulics transient benchmark problem as part of their official activities. The scope of the benchmark is to establish a well-defined problem, based on a common given library of cross sections, to compare methods and tools in core simulation and thermal hydraulics analysis with a specific focus on transient events through a set of multi-dimensional computational test problems. The benchmark includes three steady state exercises and six transient exercises. This paper describes the first two steady state exercises, their objectives and the international participation in terms of organization, country and computer code utilized. This description is followed by a comparison and analysis of the participants' results submitted for these two exercises. The comparison of results from different codes allows for an assessment of the sensitivity of a result to the method employed and can thus help to focus the development efforts on the most critical areas. The two first exercises also allow for removing of user-related modeling errors and prepare core neutronics and thermal-hydraulics models of the different codes for the rest of the exercises in the benchmark. (authors)

  10. INL Results for Phases I and III of the OECD/NEA MHTGR-350 Benchmark

    SciTech Connect (OSTI)

    Gerhard Strydom; Javier Ortensi; Sonat Sen; Hans Hammer

    2013-09-01

    The Idaho National Laboratory (INL) Very High Temperature Reactor (VHTR) Technology Development Office (TDO) Methods Core Simulation group led the construction of the Organization for Economic Cooperation and Development (OECD) Modular High Temperature Reactor (MHTGR) 350 MW benchmark for comparing and evaluating prismatic VHTR analysis codes. The benchmark is sponsored by the OECD's Nuclear Energy Agency (NEA), and the project will yield a set of reference steady-state, transient, and lattice depletion problems that can be used by the Department of Energy (DOE), the Nuclear Regulatory Commission (NRC), and vendors to assess their code suits. The Methods group is responsible for defining the benchmark specifications, leading the data collection and comparison activities, and chairing the annual technical workshops. This report summarizes the latest INL results for Phase I (steady state) and Phase III (lattice depletion) of the benchmark. The INSTANT, Pronghorn and RattleSnake codes were used for the standalone core neutronics modeling of Exercise 1, and the results obtained from these codes are compared in Section 4. Exercise 2 of Phase I requires the standalone steady-state thermal fluids modeling of the MHTGR-350 design, and the results for the systems code RELAP5-3D are discussed in Section 5. The coupled neutronics and thermal fluids steady-state solution for Exercise 3 are reported in Section 6, utilizing the newly developed Parallel and Highly Innovative Simulation for INL Code System (PHISICS)/RELAP5-3D code suit. Finally, the lattice depletion models and results obtained for Phase III are compared in Section 7. The MHTGR-350 benchmark proved to be a challenging simulation set of problems to model accurately, and even with the simplifications introduced in the benchmark specification this activity is an important step in the code-to-code verification of modern prismatic VHTR codes. A final OECD/NEA comparison report will compare the Phase I and III results

  11. B Plant facility description

    SciTech Connect (OSTI)

    Chalk, S.E.

    1996-10-04

    Buildings 225B, 272B, 282B, 282BA, and 294B were removed from the B Plant facility description. Minor corrections were made for tank sizes and hazardous and toxic inventories.

  12. Results from the OECD report on international projections of electricity generating costs

    SciTech Connect (OSTI)

    Paffenbarger, J.A.; Bertel, E.

    1998-07-01

    The International Energy Agency and Nuclear Energy Agency of the OECD have periodically undertaken a joint study on electricity generating costs in OECD Member countries and selected non-Member countries. This paper presents key results from the 1998 update of this study. Experts from 19 countries drawn from electric utility companies and government provided data on capital costs, operating and maintenance costs, and fuel costs from which levelized electricity generating costs (US cents/kWh) for baseload power plants were estimated in each country using a common set of economic assumptions. Light water nuclear power plants, pulverized coal plants, and natural gas-fired combined cycle gas turbines were the principal options evaluated. five and 10% discount rates, 40-year operating lifetime, and 75% annual load factor were the base assumptions, with sensitivity analyses on operating lifetime and load factor. Fuel costs and fuel escalation were provided individually by country, with a sensitivity case to evaluate costs assuming no real fuel price escalation over plant lifetimes. Of the three principal fuel/technology options, none is predominantly the cheapest option for all economic assumptions. However, fossil-fueled options are generally estimated to be the least expensive option. The study confirms that gas-fired combined cycles have improved their economic performance in most countries in recent years and are strong competitors to nuclear and coal-fired plants. Eleven out of the 18 countries with two or more options show gas-fired plants to be the cheapest option at 10% discount rate. Coal remains a strong competitor to gas when lower discount rates are used. Nuclear is the least expensive at both 5 and 10% discount rate in only two countries. Generally, with gas prices above 5 US$/GJ, nuclear plants constructed at overnight capital costs below 1 650 $/kWe have the potential to be competitive only at lower discount rates.

  13. BIA Description | Open Energy Information

    Open Energy Info (EERE)

    Description Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: BIA Description Abstract Description of Bureau of Indian Affairs. Author Bureau of Indian...

  14. ASP Program Description

    Office of Energy Efficiency and Renewable Energy (EERE)

    The ASP Program Description provides a general overview of the auditing, proficiency testing and field sampling planning activities in support of mission-critical DOE operations such as on-going environmental monitoring, environmental remediation, and long-term legacy management and surveillance of past field sites

  15. Description of GPRA08 scenarios

    SciTech Connect (OSTI)

    None, None

    2009-01-18

    Background information for the FY 2007 GPRA methodology review providing a description of GPRA08 scenarios.

  16. The OECD/NEA/NSC PBMR coupled neutronics/thermal hydraulics transient benchmark: The PBMR-400 core design

    SciTech Connect (OSTI)

    Reitsma, F.; Ivanov, K.; Downar, T.; De Haas, H.; Gougar, H. D.

    2006-07-01

    The Pebble Bed Modular Reactor (PBMR) is a High-Temperature Gas-cooled Reactor (HTGR) concept to be built in South Africa. As part of the verification and validation program the definition and execution of code-to-code benchmark exercises are important. The Nuclear Energy Agency (NEA) of the Organisation for Economic Cooperation and Development (OECD) has accepted, through the Nuclear Science Committee (NSC), the inclusion of the Pebble-Bed Modular Reactor (PBMR) coupled neutronics/thermal hydraulics transient benchmark problem in its program. The OECD benchmark defines steady-state and transients cases, including reactivity insertion transients. It makes use of a common set of cross sections (to eliminate uncertainties between different codes) and includes specific simplifications to the design to limit the need for participants to introduce approximations in their models. In this paper the detailed specification is explained, including the test cases to be calculated and the results required from participants. (authors)

  17. TMACS system description

    SciTech Connect (OSTI)

    Scaief, C.C.

    1995-10-17

    This document provides a description of the Tank Monitor and Control System (TMACS). It is intended as an introduction for those persons unfamiliar with the system as well as a reference document for the users, maintenance personnel, and system designers. In addition to describing the system, the document outlines the associated drawing documentation, provides maintenance and spare parts information, and discusses other TMACS documents that provide additional detail

  18. Management control system description

    SciTech Connect (OSTI)

    Bence, P. J.

    1990-10-01

    This Management Control System (MCS) description describes the processes used to manage the cost and schedule of work performed by Westinghouse Hanford Company (Westinghouse Hanford) for the US Department of Energy, Richland Operations Office (DOE-RL), Richland, Washington. Westinghouse Hanford will maintain and use formal cost and schedule management control systems, as presented in this document, in performing work for the DOE-RL. This MCS description is a controlled document and will be modified or updated as required. This document must be approved by the DOE-RL; thereafter, any significant change will require DOE-RL concurrence. Westinghouse Hanford is the DOE-RL operations and engineering contractor at the Hanford Site. Activities associated with this contract (DE-AC06-87RL10930) include operating existing plant facilities, managing defined projects and programs, and planning future enhancements. This document is designed to comply with Section I-13 of the contract by providing a description of Westinghouse Hanford's cost and schedule control systems used in managing the above activities. 5 refs., 22 figs., 1 tab.

  19. Comparison of the PHISICS/RELAP5-3D Ring and Block Model Results for Phase I of the OECD MHTGR-350 Benchmark

    SciTech Connect (OSTI)

    Gerhard Strydom

    2014-04-01

    The INL PHISICS code system consists of three modules providing improved core simulation capability: INSTANT (performing 3D nodal transport core calculations), MRTAU (depletion and decay heat generation) and a perturbation/mixer module. Coupling of the PHISICS code suite to the thermal hydraulics system code RELAP5-3D has recently been finalized, and as part of the code verification and validation program the exercises defined for Phase I of the OECD/NEA MHTGR 350 MW Benchmark were completed. This paper provides an overview of the MHTGR Benchmark, and presents selected results of the three steady state exercises 1-3 defined for Phase I. For Exercise 1, a stand-alone steady-state neutronics solution for an End of Equilibrium Cycle Modular High Temperature Reactor (MHTGR) was calculated with INSTANT, using the provided geometry, material descriptions, and detailed cross-section libraries. Exercise 2 required the modeling of a stand-alone thermal fluids solution. The RELAP5-3D results of four sub-cases are discussed, consisting of various combinations of coolant bypass flows and material thermophysical properties. Exercise 3 combined the first two exercises in a coupled neutronics and thermal fluids solution, and the coupled code suite PHISICS/RELAP5-3D was used to calculate the results of two sub-cases. The main focus of the paper is a comparison of the traditional RELAP5-3D “ring” model approach vs. a much more detailed model that include kinetics feedback on individual block level and thermal feedbacks on a triangular sub-mesh. The higher fidelity of the block model is illustrated with comparison results on the temperature, power density and flux distributions, and the typical under-predictions produced by the ring model approach are highlighted.

  20. TWRS baseline system description

    SciTech Connect (OSTI)

    Lee, A.K.

    1995-03-28

    This document provides a description of the baseline system conceptualized for remediating the tank waste stored within the Hanford Site. Remediation of the tank waste will be performed by the Tank Waste Remediation System (TWRS). This baseline system description (BSD) document has been prepared to describe the current planning basis for the TWRS for accomplishing the tank waste remediation functions. The BSD document is not intended to prescribe firm program management strategies for implementing the TWRS. The scope of the TWRS Program includes managing existing facilities, developing technology for new systems; building, testing and operating new facilities; and maintaining the system. The TWRS Program will manage the system used for receiving, safely storing, maintaining, treating, and disposing onsite, or packaging for offsite disposal, all tank waste. The scope of the TWRS Program encompasses existing facilities such as waste storage tanks, evaporators, pipelines, and low-level radioactive waste treatment and disposal facilities. It includes support facilities that comprise the total TWRS infrastructure, including upgrades to existing facilities or equipment and the addition of new facilities.

  1. OECD/NEA Ongoing activities related to the nuclear fuel cycle

    SciTech Connect (OSTI)

    Cornet, S.M.; McCarthy, K.; Chauvin, N.

    2013-07-01

    As part of its role in encouraging international collaboration, the OECD Nuclear Energy Agency is coordinating a series of projects related to the Nuclear Fuel Cycle. The Nuclear Science Committee (NSC) Working Party on Scientific Issues of the Nuclear Fuel Cycle (WPFC) comprises five different expert groups covering all aspects of the fuel cycle from front to back-end. Activities related to fuels, materials, physics, separation chemistry, and fuel cycles scenarios are being undertaken. By publishing state-of-the-art reports and organizing workshops, the groups are able to disseminate recent research advancements to the international community. Current activities mainly focus on advanced nuclear systems, and experts are working on analyzing results and establishing challenges associated to the adoption of new materials and fuels. By comparing different codes, the Expert Group on Advanced Fuel Cycle Scenarios is aiming at gaining further understanding of the scientific issues and specific national needs associated with the implementation of advanced fuel cycles. At the back end of the fuel cycle, separation technologies (aqueous and pyrochemical processing) are being assessed. Current and future activities comprise studies on minor actinides separation and post Fukushima studies. Regular workshops are also organized to discuss recent developments on Partitioning and Transmutation. In addition, the Nuclear Development Committee (NDC) focuses on the analysis of the economics of nuclear power across the fuel cycle in the context of changes of electricity markets, social acceptance and technological advances and assesses the availability of the nuclear fuel and infrastructure required for the deployment of existing and future nuclear power. The Expert Group on the Economics of the Back End of the Nuclear Fuel Cycle (EBENFC), in particular, is looking at assessing economic and financial issues related to the long term management of spent nuclear fuel. (authors)

  2. RELAP5/MOD2 assessment, OECD-LOFT small break experiment LP-SB-03

    SciTech Connect (OSTI)

    Guntay, S. )

    1990-04-01

    An analysis of the experimental results and post-test calculations using RELAP5/MOD2 carried out for OECD-LOFT small break experiment LP-SB-3 are presented. Experiment LP-SB-3 was conducted on March 5, 1984 in Loss-of-Fluid Test (LOFT) facility located at the Idaho National Engineering Laboratory (INEL). The experiment simulated a small cold leg break, with concurrent loss of high pressure injection system, and cooldown and recovery by feed and bleed of the steam generator secondary side and accumulator injection, respectively. The analysis was under taken as a part of a program at EIR aimed at developing experience in using the latest generation of best estimate Loss of Coolant Accident (LOCA) analysis computer codes, and to improve understanding of Small Break LOCA transients and as well as a part of a program aimed at assessing the RELAP5/MOD2 code. The latest available version (Cycle 33 to 36.1) of the code was used. The particular test selected for the analysis included several phenomena potentially relevant to any PWR plant operation in Switzerland. This report documents a short post-test analysis of the experiment emphasizing the results of additional analysis performed during the course of this task. RELAP5/MOD2 input model and results of the post-test calculation are documented. Included in the report are the results of a sensitivity analysis which show the predicted thermal-hydraulic response to a different input model. 7 refs., 55 figs., 2 tabs.

  3. YUCCA MOUNTAIN SITE DESCRIPTION

    SciTech Connect (OSTI)

    A.M. Simmons

    2004-04-16

    The ''Yucca Mountain Site Description'' summarizes, in a single document, the current state of knowledge and understanding of the natural system at Yucca Mountain. It describes the geology; geochemistry; past, present, and projected future climate; regional hydrologic system; and flow and transport within the unsaturated and saturated zones at the site. In addition, it discusses factors affecting radionuclide transport, the effect of thermal loading on the natural system, and tectonic hazards. The ''Yucca Mountain Site Description'' is broad in nature. It summarizes investigations carried out as part of the Yucca Mountain Project since 1988, but it also includes work done at the site in earlier years, as well as studies performed by others. The document has been prepared under the Office of Civilian Radioactive Waste Management quality assurance program for the Yucca Mountain Project. Yucca Mountain is located in Nye County in southern Nevada. The site lies in the north-central part of the Basin and Range physiographic province, within the northernmost subprovince commonly referred to as the Great Basin. The basin and range physiography reflects the extensional tectonic regime that has affected the region during the middle and late Cenozoic Era. Yucca Mountain was initially selected for characterization, in part, because of its thick unsaturated zone, its arid to semiarid climate, and the existence of a rock type that would support excavation of stable openings. In 1987, the United States Congress directed that Yucca Mountain be the only site characterized to evaluate its suitability for development of a geologic repository for high-level radioactive waste and spent nuclear fuel.

  4. (OECD Expert Group meeting on reduction of capital costs of nuclear power plants, Paris, France, July 21--26, 1989): Foreign trip report

    SciTech Connect (OSTI)

    Hudson, C.R. II

    1989-08-09

    The OECD initiated a study of means to reduce the capital costs of nuclear power plants in the latter part of 1988. To accomplish the study, an Expert Group consisting of representatives of OECD member countries was formed. The initial meeting of the Expert Group was held in November 1988. A second meeting, documented in an ORNL trip report by this author, was held in May 1989. This meeting represents the third follow-on meeting with the primary goal of reviewing the draft report written by members of the Expert Group.

  5. Program Description | Robotics Internship Program

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    March 4, 2016. Apply Now for the Robotics Internship About the Internship Program Description Start of Appointment Renewal of Appointment End of Appointment Stipend Information...

  6. Analysis of the OECD/NRC BWR Turbine Trip Benchmark by the Coupled-Code System ATHLET-QUABOX/CUBBOX

    SciTech Connect (OSTI)

    Langenbuch, S.; Schmidt, K.-D.; Velkov, K.

    2004-10-15

    The OECD/NRC boiling water reactor (BWR) turbine trip benchmark has been calculated by the coupled thermal-hydraulic neutronics system code ATHLET-QUABOX/CUBBOX developed by Gesellschaft fuer Anlagen- und Reaktorsicherheit. The results obtained for all three exercises and for the additional four hypothetical cases are presented. The physical phenomena determining the BWR pressure transient are studied and explained. The sensitivity of results to variations of the initial steady-state conditions and of parameters of the two-phase flow model is discussed. A comparison is also performed for exercise 2 between the reactor core model with 33 thermal-hydraulic channels (THCs) as specified and a reactor core model with 764 THCs using a 1:1 mapping scheme.

  7. OECD/MCCI 2-D Core Concrete Interaction (CCI) tests : final report February 28, 2006.

    SciTech Connect (OSTI)

    Farmer, M. T.; Lomperski, S.; Kilsdonk, D. J.; Aeschlimann, R. W.; Basu, S.

    2011-05-23

    reactor material database for dry cavity conditions is solely one-dimensional. Although the MACE Scoping Test was carried out with a two-dimensional concrete cavity, the interaction was flooded soon after ablation was initiated to investigate debris coolability. Moreover, due to the scoping nature of this test, the apparatus was minimally instrumented and therefore the results are of limited value from the code validation viewpoint. Aside from the MACE program, the COTELS test series also investigated 2-D CCI under flooded cavity conditions. However, the input power density for these tests was quite high relative to the prototypic case. Finally, the BETA test series provided valuable data on 2-D core concrete interaction under dry cavity conditions, but these tests focused on investigating the interaction of the metallic (steel) phase with concrete. Due to these limitations, there is significant uncertainty in the partition of energy dissipated for the ablation of concrete in the lateral and axial directions under dry cavity conditions for the case of a core oxide melt. Accurate knowledge of this 'power split' is important in the evaluation of the consequences of an ex-vessel severe accident; e.g., lateral erosion can undermine containment structures, while axial erosion can penetrate the basemat, leading to ground contamination and/or possible containment bypass. As a result of this uncertainty, there are still substantial differences among computer codes in the prediction of 2-D cavity erosion behavior under both wet and dry cavity conditions. In light of the above issues, the OECD-sponsored Melt Coolability and Concrete Interaction (MCCI) program was initiated at Argonne National Laboratory. The project conducted reactor materials experiments and associated analysis to achieve the following technical objectives: (1) resolve the ex-vessel debris coolability issue through a program that focused on providing both confirmatory evidence and test data for the coolability

  8. Detailed Course Module Description | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Detailed Course Module Description Detailed Course Module Description This document lists the course modules for building science courses offered at Cornell's Collaborator...

  9. Microscopic Description of Induced Nuclear Fission (Conference...

    Office of Scientific and Technical Information (OSTI)

    Microscopic Description of Induced Nuclear Fission Citation Details In-Document Search Title: Microscopic Description of Induced Nuclear Fission You are accessing a document ...

  10. CANISTER HANDLING FACILITY DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    J.F. Beesley

    2005-04-21

    The purpose of this facility description document (FDD) is to establish requirements and associated bases that drive the design of the Canister Handling Facility (CHF), which will allow the design effort to proceed to license application. This FDD will be revised at strategic points as the design matures. This FDD identifies the requirements and describes the facility design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This FDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This FDD is part of an iterative design process. It leads the design process with regard to the flowdown of upper tier requirements onto the facility. Knowledge of these requirements is essential in performing the design process. The FDD follows the design with regard to the description of the facility. The description provided in this FDD reflects the current results of the design process.

  11. Original Workshop Proposal and Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Notes for Vis Requirements » Original Workshop Proposal and Description Original Workshop Proposal and Description Visualization Requirements for Computational Science and Engineering Applications Proposal for a DoE Workshop to Be Held 
at the Berkeley Marina Radisson Hotel,
Berkeley, California, June 5, 2002
(date and location are tenative) Workshop Co-organizers: Bernd Hamann 
University of California-Davis Lawrence Berkeley Nat'l Lab. E. Wes Bethel 
Lawrence Berkeley Nat'l Lab.

  12. Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    & Evaluation Josh Warner, Manager Contract Administration Mike Rose, Manager Smart GridDemand Response Lee Hall, Manager Programs Brent Barclay, Manager IndustrialAg Sector...

  13. Visiting Faculty Program Program Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Visiting Faculty Program Program Description The Visiting Faculty Program seeks to increase the research competitiveness of faculty members and their students at institutions historically underrepresented in the research community in order to expand the workforce vital to Department of Energy mission areas. As part of the program, selected university/college faculty members collaborate with DOE laboratory research staff on a research project of mutual interest. Program Objective The program is

  14. Student Internship Programs Program Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Student Internship Programs Program Description The objective of the Laboratory's student internship programs is to provide students with opportunities for meaningful hands- on experience supporting educational progress in their selected scientific or professional fields. The most significant impact of these internship experiences is observed in the intellectual growth experienced by the participants. Student interns are able to appreciate the practical value of their education efforts in their

  15. Sixteen Years of International Co-operation. The OECD/NEA Co-operative Programme on Decommissioning

    SciTech Connect (OSTI)

    Menon, S.; Valencia, L.

    2002-02-25

    The Co-operative Programme on Decommissioning under the administration of the Radioactive Waste Management Committee of the OECD Nuclear Energy Agency (NEA) has recently completed sixteen years of operation. The Programme, which is essentially an information exchange programme between decommissioning projects, came into being in 1985. It has grown from an initial 10 decommissioning projects from 7 countries to 39 projects from 14 countries today. From purely information exchange to start with, the Programme has, in later years, been functioning as a voice for the collective expression of views of the implementers of nuclear decommissioning. During the first sixteen years of the operation of the Co-operative Programme, nuclear decommissioning has grown from local specialist activities within projects to a competitive commercial industry. By the dismantling and release from regulatory control of over a dozen diverse nuclear facilities, the Programme has been able to demonstrate in practice, that nuclear decommissioning can be performed safely both for the workers and the public, and that this can be done at reasonable costs in an environmentally friendly fashion. During the recent years, discussions and work within the Co-operative Programme, specially within some of the Task Groups, have had/are having effects and repercussions not just in the field of nuclear decommissioning, but can possibly affect activities and regulations in other industries. This paper describes how the Programme and its activities and procedures have evolved over the years and indicate the directions of developments in the organization and execution of decommissioning projects. Finally, it gives a brief overview of the achievements of the Cooperative Programme and visualizes future developments in the field of nuclear decommissioning.

  16. SNF AGING SYSTEM DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    L.L. Swanson

    2005-04-06

    The purpose of this system description document (SDD) is to establish requirements that drive the design of the spent nuclear fuel (SNF) aging system and associated bases, which will allow the design effort to proceed. This SDD will be revised at strategic points as the design matures. This SDD identifies the requirements and describes the system design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This SDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This SDD is part of an iterative design process. It leads the design process with regard to the flow down of upper tier requirements onto the system. Knowledge of these requirements is essential in performing the design process. The SDD follows the design with regard to the description of the system. The description provided in the SDD reflects the current results of the design process. Throughout this SDD, the term aging cask applies to vertical site-specific casks and to horizontal aging modules. The term overpack is a vertical site-specific cask that contains a dual-purpose canister (DPC) or a disposable canister. Functional and operational requirements applicable to this system were obtained from ''Project Functional and Operational Requirements'' (F&OR) (Curry 2004 [DIRS 170557]). Other requirements that support the design process were taken from documents such as ''Project Design Criteria Document'' (PDC) (BSC 2004 [DES 171599]), ''Site Fire Hazards Analyses'' (BSC 2005 [DIRS 172174]), and ''Nuclear Safety Design Bases for License Application'' (BSC 2005 [DIRS 171512]). The documents address requirements in the ''Project Requirements Document'' (PRD) (Canori and Leitner 2003 [DIRS 166275]). This SDD includes several appendices. Appendix A is a Glossary; Appendix B is a list of key system charts, diagrams, drawings, lists and additional supporting information; and Appendix C is a list of

  17. ELECTRICAL SUPPORT SYSTEM DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    S. Roy

    2004-06-24

    The purpose of this revision of the System Design Description (SDD) is to establish requirements that drive the design of the electrical support system and their bases to allow the design effort to proceed to License Application. This SDD is a living document that will be revised at strategic points as the design matures over time. This SDD identifies the requirements and describes the system design as they exist at this time, with emphasis on those attributes of the design provided to meet the requirements. This SDD has been developed to be an engineering tool for design control. Accordingly, the primary audience/users are design engineers. This type of SDD both ''leads'' and ''trails'' the design process. It leads the design process with regard to the flow down of upper tier requirements onto the system. Knowledge of these requirements is essential in performing the design process. The SDD trails the design with regard to the description of the system. The description provided in the SDD is a reflection of the results of the design process to date. Functional and operational requirements applicable to electrical support systems are obtained from the ''Project Functional and Operational Requirements'' (F&OR) (Siddoway 2003). Other requirements to support the design process have been taken from higher-level requirements documents such as the ''Project Design Criteria Document'' (PDC) (Doraswamy 2004), and fire hazards analyses. The above-mentioned low-level documents address ''Project Requirements Document'' (PRD) (Canon and Leitner 2003) requirements. This SDD contains several appendices that include supporting information. Appendix B lists key system charts, diagrams, drawings, and lists, and Appendix C includes a list of system procedures.

  18. Descriptive Model of Generic WAMS

    SciTech Connect (OSTI)

    Hauer, John F.; DeSteese, John G.

    2007-06-01

    The Department of Energys (DOE) Transmission Reliability Program is supporting the research, deployment, and demonstration of various wide area measurement system (WAMS) technologies to enhance the reliability of the Nations electrical power grid. Pacific Northwest National Laboratory (PNNL) was tasked by the DOE National SCADA Test Bed Program to conduct a study of WAMS security. This report represents achievement of the milestone to develop a generic WAMS model description that will provide a basis for the security analysis planned in the next phase of this study.

  19. Microsoft Word - 338M_Geothermal_Project_Descriptions | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    338MGeothermalProjectDescriptions Microsoft Word - 338MGeothermalProjectDescriptions PDF icon Microsoft Word - 338MGeothermalProjectDescriptions More Documents & ...

  20. Slice Product Description (contracts/slice)

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    meeting on March 4, 1999, to discuss the Slice Product Description and to receive oral comments. This report summarizes the issues raised in written and oral comments...

  1. Postdoctoral Program Program Description The Postdoctoral (Postdoc...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Postdoctoral Program Program Description The Postdoctoral (Postdoc) Research program offers the opportunity for appointees to perform research in a robust scientific R&D...

  2. Investigation and Analytical Description of Acoustic Production...

    Office of Scientific and Technical Information (OSTI)

    Journal Article: Investigation and Analytical Description of Acoustic Production by Magneto-Acoustic Mixing Technology Citation Details In-Document Search This content will become...

  3. MediaWiki:Mainpage-description | Open Energy Information

    Open Energy Info (EERE)

    Mainpage-description Jump to: navigation, search Main page Retrieved from "http:en.openei.orgwikiMediaWiki:Mainpage-description...

  4. Description of Energy Intensity Tables (12)

    U.S. Energy Information Administration (EIA) Indexed Site

    3. Description of Energy Intensity Data Tables There are 12 data tables used as references for this report. Specifically, these tables are categorized as tables 1 and 2 present...

  5. CHP R&D Project Descriptions

    Office of Energy Efficiency and Renewable Energy (EERE)

    The CHP R&D project portfolio includes advanced reciprocating engine systems (ARES), packaged CHP systems, high-value applications, fuel-flexible CHP, and demonstrations of these technologies. Project fact sheets and short project descriptions are provided below:

  6. CleanEnergyProjectsonTribalLands_Project_Descriptions_072011...

    Broader source: Energy.gov (indexed) [DOE]

    CleanEnergyProjectsonTribalLandsProjectDescriptions072011.pdf More Documents & Publications CleanEnergyProjectsonTribalLandsProjectDescriptions072011.pdf...

  7. Nuclear Waste Partnership (NWP) Quality Assurance Program Description...

    Office of Environmental Management (EM)

    Waste Partnership (NWP) Quality Assurance Program Description (QAPD) Nuclear Waste Partnership (NWP) Quality Assurance Program Description (QAPD) The documents included in this ...

  8. Integrated Program Management Report (IPMR) Data Item Description...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Integrated Program Management Report (IPMR) Data Item Description (DID) Integrated Program Management Report (IPMR) Data Item Description (DID) Integrated Program Management Report...

  9. Microsoft Word - 564M_Biomass_Project Descriptions FINAL 120409...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Microsoft Word - 564MBiomassProject Descriptions FINAL 120409 Microsoft Word - 564MBiomassProject Descriptions FINAL 120409 (100.66 KB) More Documents & Publications ...

  10. Microscopic Description of Nuclear Fission: Fission Barrier Heights...

    Office of Scientific and Technical Information (OSTI)

    Conference: Microscopic Description of Nuclear Fission: Fission Barrier Heights of Even-Even Actinides Citation Details In-Document Search Title: Microscopic Description of Nuclear ...

  11. Description of Induced Nuclear Fission with Skyrme Energy Functionals...

    Office of Scientific and Technical Information (OSTI)

    Description of Induced Nuclear Fission with Skyrme Energy Functionals: II. Finite Temperature Effects Citation Details In-Document Search Title: Description of Induced Nuclear ...

  12. SURFACE INDUSTRIAL HVAC SYSTEM DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    M.M. Ansari

    2005-04-05

    The purpose of this system description document (SDD) is to establish requirements that drive the design of the surface industrial heating, ventilation, and air-conditioning (HVAC) system and its bases to allow the design effort to proceed to license application. This SDD will be revised at strategic points as the design matures. This SDD identifies the requirements and describes the system design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This SDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This SDD is part of an iterative design process. It leads the design process with regard to the flowdown of upper tier requirements onto the system. Knowledge of these requirements is essential to performing the design process. The SDD follows the design with regard to the description of the system. The description that provided in this SDD reflects the current results of the design process.

  13. Comparison of the PHISICS/RELAP5-3D ring and block model results for phase I of the OECD/NEA MHTGR-350 benchmark

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Strydom, G.; Epiney, A. S.; Alfonsi, Andrea; Rabiti, Cristian

    2015-12-02

    The PHISICS code system has been under development at INL since 2010. It consists of several modules providing improved coupled core simulation capability: INSTANT (3D nodal transport core calculations), MRTAU (depletion and decay heat generation) and modules performing criticality searches, fuel shuffling and generalized perturbation. Coupling of the PHISICS code suite to the thermal hydraulics system code RELAP5-3D was finalized in 2013, and as part of the verification and validation effort the first phase of the OECD/NEA MHTGR-350 Benchmark has now been completed. The theoretical basis and latest development status of the coupled PHISICS/RELAP5-3D tool are described in more detailmore » in a concurrent paper. This paper provides an overview of the OECD/NEA MHTGR-350 Benchmark and presents the results of Exercises 2 and 3 defined for Phase I. Exercise 2 required the modelling of a stand-alone thermal fluids solution at End of Equilibrium Cycle for the Modular High Temperature Reactor (MHTGR). The RELAP5-3D results of four sub-cases are discussed, consisting of various combinations of coolant bypass flows and material thermophysical properties. Exercise 3 required a coupled neutronics and thermal fluids solution, and the PHISICS/RELAP5-3D code suite was used to calculate the results of two sub-cases. The main focus of the paper is a comparison of results obtained with the traditional RELAP5-3D “ring” model approach against a much more detailed model that include kinetics feedback on individual block level and thermal feedbacks on a triangular sub-mesh. The higher fidelity that can be obtained by this “block” model is illustrated with comparison results on the temperature, power density and flux distributions. Furthermore, it is shown that the ring model leads to significantly lower fuel temperatures (up to 10%) when compared with the higher fidelity block model, and that the additional model development and run-time efforts are worth the gains obtained

  14. Comparison of the PHISICS/RELAP5-3D ring and block model results for phase I of the OECD/NEA MHTGR-350 benchmark

    SciTech Connect (OSTI)

    Strydom, G.; Epiney, A. S.; Alfonsi, Andrea; Rabiti, Cristian

    2015-12-02

    The PHISICS code system has been under development at INL since 2010. It consists of several modules providing improved coupled core simulation capability: INSTANT (3D nodal transport core calculations), MRTAU (depletion and decay heat generation) and modules performing criticality searches, fuel shuffling and generalized perturbation. Coupling of the PHISICS code suite to the thermal hydraulics system code RELAP5-3D was finalized in 2013, and as part of the verification and validation effort the first phase of the OECD/NEA MHTGR-350 Benchmark has now been completed. The theoretical basis and latest development status of the coupled PHISICS/RELAP5-3D tool are described in more detail in a concurrent paper. This paper provides an overview of the OECD/NEA MHTGR-350 Benchmark and presents the results of Exercises 2 and 3 defined for Phase I. Exercise 2 required the modelling of a stand-alone thermal fluids solution at End of Equilibrium Cycle for the Modular High Temperature Reactor (MHTGR). The RELAP5-3D results of four sub-cases are discussed, consisting of various combinations of coolant bypass flows and material thermophysical properties. Exercise 3 required a coupled neutronics and thermal fluids solution, and the PHISICS/RELAP5-3D code suite was used to calculate the results of two sub-cases. The main focus of the paper is a comparison of results obtained with the traditional RELAP5-3D “ring” model approach against a much more detailed model that include kinetics feedback on individual block level and thermal feedbacks on a triangular sub-mesh. The higher fidelity that can be obtained by this “block” model is illustrated with comparison results on the temperature, power density and flux distributions. Furthermore, it is shown that the ring model leads to significantly lower fuel temperatures (up to 10%) when compared with the higher fidelity block model, and that the additional model development and run-time efforts are worth the gains obtained in the

  15. Description of the RDCDS Meteorological Component

    SciTech Connect (OSTI)

    Pekour, Mikhail S.; Berg, Larry K.

    2007-10-01

    This report provides a detailed description of the Rapidly Deployable Chemical Defense System (RDCDS) Meteorological Component. The Meteorological Component includes four surface meteorological stations, miniSODAR, laptop computers, and communications equipment. This report describes the equipment that is used, explains the operation of the network, and gives instructions for setting up the Component and replacing defective parts. A detailed description of operation and use of the individual sensors, including the data loggers is not covered in the current document, and the interested reader should refer to the manufacturer’s documentation.

  16. TWRS information locator database system design description

    SciTech Connect (OSTI)

    Knutson, B.J.

    1996-09-13

    This document gives an overview and description of the Tank Waste Remediation System (TWRS) Information Locator Database (ILD)system design. The TWRS ILD system is an inventory of information used in the TWRS Systems Engineering process to represent the TWRS Technical Baseline. The inventory is maintained in the form of a relational database developed in Paradox 4.5.

  17. Network architecture functional description and design

    SciTech Connect (OSTI)

    Stans, L.; Bencoe, M.; Brown, D.; Kelly, S.; Pierson, L.; Schaldach, C.

    1989-05-25

    This report provides a top level functional description and design for the development and implementation of the central network to support the next generation of SNL, Albuquerque supercomputer in a UNIX{reg sign} environment. It describes the network functions and provides an architecture and topology.

  18. Better Buildings Neighborhood Program Business Models Guide: Program Administrator Description

    Broader source: Energy.gov [DOE]

    Better Buildings Neighborhood Program Business Models Guide: Program Administrator Business Models, Program Administrator Description.

  19. System Design Description PFP Thermal Stabilization

    SciTech Connect (OSTI)

    RISENMAY, H.R.

    2000-04-25

    The purpose of this document is to provide a system design description (SDD) and design basis for the Plutonium Finishing Plant (PFP) Thermal Stabilization project. The chief objective of the SDD is to document the Structures, Systems, and Components (SSCs) that establish and maintain the facility Safety Envelope necessary for normal safe operation of the facility; as identified in the FSAR, the OSRs, and Safety Assessment Documents (SADs). This safety equipment documentation should satisfy guidelines for the SDD given in WHC-SD-CP-TI-18 1, Criteria for Identification and Control of Equipment Necessary for Preservation of the Safety Envelope and Safe Operation of PFP. The basis for operational, alarm response, maintenance, and surveillance procedures are also identified and justified in this document. This document and its appendices address the following elements of the PFP Thermal Stabilization project: Functional and design requirements; Design description; Safety Envelope Analysis; Safety Equipment Class; and Operational, maintenance and surveillance procedures.

  20. Acquisition Description/ Category Solicitation Method Contract Type

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    7/5/2016 Acquisition Description/ Category Solicitation Method Contract Type Period of Performance Contract Value All EM Sites DOE-Wide commercial low-level waste treatment Energy Solutions, Inc. Perma-Fix Environmental Services, Inc. Philo-Technics, Ltd. Studsvik, Inc. Full and Open Competition Firm Fixed Price IDIQ 6/30/08-6/29/13 $450M Multiple award indefinite delivery/indefinite quality (IDIQ) Set-aside contracts for nationwide environmental services/ environmental cleanup Clauss

  1. Certificate in Environmental Monitoring Program Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Certificate in Environmental Monitoring Program Description Since a primary goal of the Neighborhood Environmental Watch Network (NEWNET) project is to provide information to the public, it is fitting that there are appropriate education programs. NEWNET has collaborated with several local high schools and colleges by providing them with local NEWNET stations. Some teaching curricula include a study of radiation and detection, data acquisition and plotting, meteorology, or uses of computers.

  2. Machinist Pipeline/Apprentice Program Program Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Machinist Pipeline/Apprentice Program Program Description The Machinist Pipeline Program was created by the Prototype Fabrication Division to fill a critical need for skilled journeyworker machinists. It is based on a program developed by the National Institute for Metalworking Skills (NIMS) in conjunction with metalworking trade associations to develop and maintain a globally competitive U.S. workforce. The goal is to develop and implement apprenticeship programs that are aligned with

  3. INCOMING DOCUMENT CONTROL FORM DOCUMENT DESCRIPTION ORGANIZATIO

    Office of Legacy Management (LM)

    INCOMING DOCUMENT CONTROL FORM DOCUMENT DESCRIPTION ORGANIZATIO )ATE COMPLETED: ACTION NUMBER: I ! I I DOCUMENT CONTROL DATE INITIALS DATA BASE: ACTION LOG: FILED: To : Doug Tonkay, OTS Decen From: MIchele Landis, dRW Subject: Draft report ~ Result= of the Radiologic; Former Ore Storage Site, Palmerton, Pennsylvania Attached is one copy of the draft report. PIE provide your comments to me by January 16, 1990. tlichele Landis ,9, 1989 "ey at the review and Results of the Radiological SJrvey

  4. Project_Descriptions_ITP_ARRA_Awards.xls

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Selections for Industrial Technologies Program Recovery Act Funding Deployment of Combined Heat and Power (CHP) Systems, District Energy Systems, Waste Energy Recovery Systems, and Efficient Industrial Equipment Award Winners City and State Project Description Total DOE Funding Air Products and Chemicals, Inc. Middletown, OH Waste Energy Project at the AK Steel Corporation Middletown Works. The project will construct a combined cycle power generation plant at the Middletown, OH, works of AK

  5. Status Report on Activities of the Systems Assessment Task Force, OECD-NEA Expert Group on Accident Tolerant Fuels for LWRs

    SciTech Connect (OSTI)

    Bragg-Sitton, Shannon Michelle

    2015-09-01

    The Organization for Economic Cooperation and Development /Nuclear Energy Agency (OECD/NEA) Nuclear Science Committee approved the formation of an Expert Group on Accident Tolerant Fuel (ATF) for LWRs (EGATFL) in 2014. Chaired by Kemal Pasamehmetoglu, INL Associate Laboratory Director for Nuclear Science and Technology, the mandate for the EGATFL defines work under three task forces: (1) Systems Assessment, (2) Cladding and Core Materials, and (3) Fuel Concepts. Scope for the Systems Assessment task force includes definition of evaluation metrics for ATF, technology readiness level definition, definition of illustrative scenarios for ATF evaluation, parametric studies, and selection of system codes. The Cladding and Core Materials and Fuel Concepts task forces will identify gaps and needs for modeling and experimental demonstration; define key properties of interest; identify the data necessary to perform concept evaluation under normal conditions and illustrative scenarios; identify available infrastructure (internationally) to support experimental needs; and make recommendations on priorities. Where possible, considering proprietary and other export restrictions (e.g., International Traffic in Arms Regulations), the Expert Group will facilitate the sharing of data and lessons learned across the international group membership. The Systems Assessment Task Force is chaired by Shannon Bragg-Sitton (INL), while the Cladding Task Force will be chaired by a representative from France (Marie Moatti, Electricite de France [EdF]) and the Fuels Task Force will be chaired by a representative from Japan (Masaki Kurata, Japan Atomic Energy Agency [JAEA]). This report provides an overview of the Systems Assessment Task Force charter and status of work accomplishment.

  6. Hamiltonian description of the ideal fluid

    SciTech Connect (OSTI)

    Morrison, P.J.

    1994-01-01

    Fluid mechanics is examined from a Hamiltonian perspective. The Hamiltonian point of view provides a unifying framework; by understanding the Hamiltonian perspective, one knows in advance (within bounds) what answers to expect and what kinds of procedures can be performed. The material is organized into five lectures, on the following topics: rudiments of few-degree-of-freedom Hamiltonian systems illustrated by passive advection in two-dimensional fluids; functional differentiation, two action principles of mechanics, and the action principle and canonical Hamiltonian description of the ideal fluid; noncanonical Hamiltonian dynamics with examples; tutorial on Lie groups and algebras, reduction-realization, and Clebsch variables; and stability and Hamiltonian systems.

  7. Date Time Event Description/Participants Location

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Updated: 06/11/2015 Date Time Event Description/Participants Location Point of Contact 11 thru 12 All Day Meeting Todd Allen, deputy director of Science and Technology at INL, has been invited to speak at the Idaho Society of Professional Engineers (ISPE) annual meeting. Coeur d'Alene, ID Sara Prentice, 526-9591 18 9:00 AM Education Outreach Approximately 50 iSTEM students and instructors will tour various INL Idaho Falls facilities Idaho Falls, ID INL Tours Office, 526-0050 23 All Day Meeting

  8. STEP Energy Coach and Technical Consultant Job Descriptions

    Broader source: Energy.gov [DOE]

    STEP Energy Coach and Technical Consultant Job Descriptions, from the Tool Kit Framework: Small Town University Energy Program (STEP).

  9. COG Software Architecture Design Description Document

    SciTech Connect (OSTI)

    Buck, R M; Lent, E M

    2009-09-21

    This COG Software Architecture Design Description Document describes the organization and functionality of the COG Multiparticle Monte Carlo Transport Code for radiation shielding and criticality calculations, at a level of detail suitable for guiding a new code developer in the maintenance and enhancement of COG. The intended audience also includes managers and scientists and engineers who wish to have a general knowledge of how the code works. This Document is not intended for end-users. This document covers the software implemented in the standard COG Version 10, as released through RSICC and IAEA. Software resources provided by other institutions will not be covered. This document presents the routines grouped by modules and in the order of the three processing phases. Some routines are used in multiple phases. The routine description is presented once - the first time the routine is referenced. Since this is presented at the level of detail for guiding a new code developer, only the routines invoked by another routine that are significant for the processing phase that is being detailed are presented. An index to all routines detailed is included. Tables for the primary data structures are also presented.

  10. Guam: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    EIA Natural Gas Reserves Unavailable Cubic Meters (cu m) NA 2010 CIA World Factbook Oil Reserves Unavailable Barrels (bbl) NA 2010 CIA World Factbook Energy Maps featuring...

  11. American Samoa: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    EIA Natural Gas Reserves Unavailable Cubic Meters (cu m) NA 2010 CIA World Factbook Oil Reserves Unavailable Barrels (bbl) NA 2010 CIA World Factbook Energy Maps featuring...

  12. Republic of the Congo: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    EIA Natural Gas Reserves Unavailable Cubic Meters (cu m) NA 2010 CIA World Factbook Oil Reserves Unavailable Barrels (bbl) NA 2010 CIA World Factbook Energy Maps featuring...

  13. AHTR Refueling Systems and Process Description

    SciTech Connect (OSTI)

    Varma, Venugopal Koikal; Holcomb, David Eugene; Bradley, Eric Craig; Zaharia, Nathaniel M; Cooper, Eliott J

    2012-07-01

    The Advanced High-Temperature Reactor (AHTR) is a design concept for a central station-type [1500 MW(e)] Fluoride salt-cooled High-temperature Reactor (FHR) that is currently undergoing development by Oak Ridge National Laboratory for the US. Department of Energy, Office of Nuclear Energy's Advanced Reactor Concepts program. FHRs, by definition, feature low-pressure liquid fluoride salt cooling, coated-particle fuel, a high-temperature power cycle, and fully passive decay heat rejection. The overall goal of the AHTR development program is to demonstrate the technical feasibility of FHRs as low-cost, large-size power producers while maintaining full passive safety. The AHTR is approaching a preconceptual level of maturity. An initial integrated layout of its major systems, structures, and components (SSCs), and an initial, high-level sequence of operations necessary for constructing and operating the plant is nearing completion. An overview of the current status of the AHTR concept has been recently published and a report providing a more detailed overview of the AHTR structures and mechanical systems is currently in preparation. This report documents the refueling components and processes envisioned at this early development phase. The report is limited to the refueling aspects of the AHTR and does not include overall reactor or power plant design information. The report, however, does include a description of the materials envisioned for the various components and the instrumentation necessary to control the refueling process. The report begins with an overview of the refueling strategy. Next a mechanical description of the AHTR fuel assemblies and core is provided. The reactor vessel upper assemblies are then described. Following this the refueling path structures and the refueling mechanisms and components are described. The sequence of operations necessary to fuel and defuel the reactor is then discussed. The report concludes with a discussion of the levels of

  14. AHTR Refueling Systems and Process Description

    SciTech Connect (OSTI)

    Varma, V.K.; Holcomb, D.E.; Bradley, E.C.; Zaharia, N.M.; Cooper, E.J.

    2012-07-15

    The Advanced High-Temperature Reactor (AHTR) is a design concept for a central station-type [1500 MW(e)] Fluoride salt–cooled High-temperature Reactor (FHR) that is currently undergoing development by Oak Ridge National Laboratory for the US. Department of Energy, Office of Nuclear Energy’s Advanced Reactor Concepts program. FHRs, by definition, feature low-pressure liquid fluoride salt cooling, coated-particle fuel, a high-temperature power cycle, and fully passive decay heat rejection. The overall goal of the AHTR development program is to demonstrate the technical feasibility of FHRs as low-cost, large-size power producers while maintaining full passive safety. The AHTR is approaching a preconceptual level of maturity. An initial integrated layout of its major systems, structures, and components (SSCs), and an initial, high-level sequence of operations necessary for constructing and operating the plant is nearing completion. An overview of the current status of the AHTR concept has been recently published [1], and a report providing a more detailed overview of the AHTR structures and mechanical systems is currently in preparation. This report documents the refueling components and processes envisioned at this early development phase. The report is limited to the refueling aspects of the AHTR and does not include overall reactor or power plant design information. The report, however, does include a description of the materials envisioned for the various components and the instrumentation necessary to control the refueling process. The report begins with an overview of the refueling strategy. Next a mechanical description of the AHTR fuel assemblies and core is provided. The reactor vessel upper assemblies are then described. Following this the refueling path structures and the refueling mechanisms and components are described. The sequence of operations necessary to fuel and defuel the reactor is then discussed. The report concludes with a discussion of the

  15. Hot Spot Removal System: System description

    SciTech Connect (OSTI)

    1997-09-01

    Hazardous wastes contaminated with radionuclides, chemicals, and explosives exist across the Department of Energy complex and need to be remediated due to environmental concerns. Currently, an opportunity is being developed to dramatically reduce remediation costs and to assist in the acceleration of schedules associated with these wastes by deploying a Hot Spot Removal System. Removing the hot spot from the waste site will remove risk driver(s) and enable another, more cost effective process/option/remedial alternative (i.e., capping) to be applied to the remainder of the site. The Hot Spot Removal System consists of a suite of technologies that will be utilized to locate and remove source terms. Components of the system can also be used in a variety of other cleanup activities. This Hot Spot Removal System Description document presents technologies that were considered for possible inclusion in the Hot Spot Removal System, technologies made available to the Hot Spot Removal System, industrial interest in the Hot Spot Removal System`s subsystems, the schedule required for the Hot Spot Removal System, the evaluation of the relevant technologies, and the recommendations for equipment and technologies as stated in the Plan section.

  16. CHP R&D Project Descriptions | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    CHP R&D Project Descriptions CHP R&D Project Descriptions The CHP R&D project portfolio includes advanced reciprocating engine systems (ARES), packaged CHP systems, high-value applications, fuel-flexible CHP, and demonstrations of these technologies. Project fact sheets and short project descriptions are provided below: Advanced Reciprocating Engine Systems Advanced Reciprocating Engine Systems (ARES) The ARES program is designed to promote separate, but parallel engine development

  17. 2015 ASP Program Report Description | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ASP Program Report Description 2015 ASP Program Report Description This report provides an overview of the ASP's activities for Fiscal Year (FY) 2015 for the United States (U.S.) Department of Energy (DOE or Department), including the National Nuclear Security Administration (NNSA). The ASP is managed by the Office of Environment, Health, Safety and Security (AU), Office of Sustainable Environmental Stewardship. The ASP fiscal year reports supplement the ASP Program Description, March 2016,

  18. TITLE AUTHORS SUBJECT SUBJECT RELATED DESCRIPTION PUBLISHER AVAILABILI...

    Office of Scientific and Technical Information (OSTI)

    the experimental method and Free Precession Method descriptions and then experimental design elements ending with a summary A new nEDM experiment is under development with a...

  19. Description of Induced Nuclear Fission with Skyrme Energy Functionals...

    Office of Scientific and Technical Information (OSTI)

    Fragment Properties Citation Details In-Document Search Title: Description of Induced Nuclear Fission with Skyrme Energy Functionals: I. Static Potential Energy Surfaces and...

  20. Microscopic description of fission dynamics: finite element method...

    Office of Scientific and Technical Information (OSTI)

    Title: Microscopic description of fission dynamics: finite element method resolution of ... This site is a product of DOE's Office of Scientific and Technical Information (OSTI) and ...

  1. Nevada Test Site Environmental Report Attachment A: Site Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nevada Test Site Environmental Report Attachment A: Site Description DOENV25946--790-ATT A Nevada Test Site Environmental Report 2008 Disclaimer Reference herein to any specific ...

  2. Descriptions of ESPC Task Order Schedules and Placement of Pricing...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Pricing Information (IDIQ Attachment J-5) Descriptions of ESPC Task Order Schedules and Placement of Pricing Information (IDIQ Attachment J-5) Document provides task order ...

  3. Description of induced nuclear fission with Skyrme energy functionals...

    Office of Scientific and Technical Information (OSTI)

    Citation Details In-Document Search Title: Description of induced nuclear fission with Skyrme energy functionals: Static potential energy surfaces and fission fragment properties ...

  4. Section I - FUNDING OPPORTUNITY DESCRIPTION | Department of Energy

    Broader source: Energy.gov (indexed) [DOE]

    Section I - FUNDING OPPORTUNITY DESCRIPTION More Documents & Publications U. S. Department of Energy - Headquarters Advanced Research Projects Agency Advanced Research Projects...

  5. Unified description of superconducting pairing symmetry in electron...

    Office of Scientific and Technical Information (OSTI)

    Title: Unified description of superconducting pairing symmetry in electron-doped Fe-based-... Type: Publisher's Accepted Manuscript Journal Name: Physical Review B Additional Journal ...

  6. Description of the proton and neutron radiative capture reactions...

    Office of Scientific and Technical Information (OSTI)

    Description of the proton and neutron radiative capture reactions in the Gamow shell model Not Available Temp HTML Storage 2: Fossez, K.; Michel, N.; Poszajczak, M.; Jaganathen, ...

  7. TITLE AUTHORS SUBJECT SUBJECT RELATED DESCRIPTION PUBLISHER AVAILABILI...

    Office of Scientific and Technical Information (OSTI)

    further description Trainor Guitton Hoversten Nordquist Intani Value of information analysis using geothermal field data accounting for multiple interpretations determining new...

  8. Tribal Energy Program February 2012 Award Project Descriptions...

    Energy Savers [EERE]

    PDF icon Tribal Energy Program Feb 2012 Awards Project Descriptions0.pdf More Documents & Publications Community-Scale Project Development and Finance Workshop Agenda and ...

  9. Tank Monitor and Control System (TMACS) Version Description Document (VDD)

    SciTech Connect (OSTI)

    BARNES, D.A.

    2000-07-06

    This document updates the Version Description Document with the changes incorporated in the Revision 12.0 software installation on the Tank Monitor and Control System (TMACS).

  10. New Mexico Hydrogen Fuels Challenge Program Description The New...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    New Mexico Hydrogen Fuels Challenge Program Description The New Mexico Hydrogen Fuels Challenge is an event that provides a hands-on opportunity for middle school students (grades...

  11. name SRSCRO description url http www srscro org namespaces oembed...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    description url http www srscro org namespaces oembed authentication routes namespace methods GET endpoints methods GET args context required false default view links self http...

  12. Part III: Section C - Description, Specification, Statement of Work

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    SECTION C DESCRIPTION/SPECIFICATION/ STATEMENT OF WORK DE-AC36-08GO28308 Modification M901 Section C - Page ii PART I SECTION C DESCRIPTION/SPECIFICATION/ STATEMENT OF WORK TABLE OF CONTENTS C.1 Introduction ............................................................................................................ 1 C.2 Purpose ................................................................................................................... 2 C.3 Background

  13. DOE-RL Integrated Safety Management System Description

    SciTech Connect (OSTI)

    SHOOP, D.S.

    2000-09-01

    The purpose of this Integrated Safety Management System Description (ISMSD) is to describe the U.S. Department of Energy (DOE), Richland Operations Office (RL) ISMS as implemented through the RL Integrated Management System (RIMS). This ISMSD does not impose additional requirements but rather provides an overview describing how various parts of the ISMS fit together. Specific requirements for each of the core functions and guiding principles are established in other implementing processes, procedures, and program descriptions that comprise RIMS. RL is organized to conduct work through operating contracts; therefore, it is extremely difficult to provide an adequate ISMS description that only addresses RL functions. Of necessity, this ISMSD contains some information on contractor processes and procedures which then require RL approval or oversight. This ISMSD does not purport to contain a full description of the contractors' ISM System Descriptions.

  14. New Multi-group Transport Neutronics (PHISICS) Capabilities for RELAP5-3D and its Application to Phase I of the OECD/NEA MHTGR-350 MW Benchmark

    SciTech Connect (OSTI)

    Gerhard Strydom; Cristian Rabiti; Andrea Alfonsi

    2012-10-01

    PHISICS is a neutronics code system currently under development at the Idaho National Laboratory (INL). Its goal is to provide state of the art simulation capability to reactor designers. The different modules for PHISICS currently under development are a nodal and semi-structured transport core solver (INSTANT), a depletion module (MRTAU) and a cross section interpolation (MIXER) module. The INSTANT module is the most developed of the mentioned above. Basic functionalities are ready to use, but the code is still in continuous development to extend its capabilities. This paper reports on the effort of coupling the nodal kinetics code package PHISICS (INSTANT/MRTAU/MIXER) to the thermal hydraulics system code RELAP5-3D, to enable full core and system modeling. This will enable the possibility to model coupled (thermal-hydraulics and neutronics) problems with more options for 3D neutron kinetics, compared to the existing diffusion theory neutron kinetics module in RELAP5-3D (NESTLE). In the second part of the paper, an overview of the OECD/NEA MHTGR-350 MW benchmark is given. This benchmark has been approved by the OECD, and is based on the General Atomics 350 MW Modular High Temperature Gas Reactor (MHTGR) design. The benchmark includes coupled neutronics thermal hydraulics exercises that require more capabilities than RELAP5-3D with NESTLE offers. Therefore, the MHTGR benchmark makes extensive use of the new PHISICS/RELAP5-3D coupling capabilities. The paper presents the preliminary results of the three steady state exercises specified in Phase I of the benchmark using PHISICS/RELAP5-3D.

  15. Microsoft Word - Appendix D_LegalDescription.doc

    Office of Legacy Management (LM)

    for the Chemical Plant Area Weldon Spring Site LTS&M Plan U.S. Department of Energy Doc. No. S0079000 July 2005 Page D-4 Legal Description for the Chemical Plant Area All that ...

  16. Hanford Site existing irradiated fuel storage facilities description

    SciTech Connect (OSTI)

    Willis, W.L.

    1995-01-11

    This document describes facilities at the Hanford Site which are currently storing spent nuclear fuels. The descriptions provide a basis for the no-action alternatives of ongoing and planned National Environmental Protection Act reviews.

  17. OMB 1910-5122, Human Reliability Program - Description of Collections |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy OMB 1910-5122, Human Reliability Program - Description of Collections OMB 1910-5122, Human Reliability Program - Description of Collections Human Reliability Program Certification (DOE F 470.3). Under the Department of Energy Human Reliability Program (HRP), individuals who are applicants for or incumbents in designated positions must be evaluated to ensure that they meet the requirements for certification in the program. This form documents that each part of the

  18. Summary description of the Fast Flux Test Facility

    SciTech Connect (OSTI)

    Cabell, C.P.

    1980-12-01

    This document has been compiled and issued to provide an illustrated engineering summary description of the FFTF. The document is limited to a description of the plant and its functions, and does not cover the extensive associated programs that have been carried out in the fields of design, design analysis, safety analysis, fuels development, equipment development and testing, quality assurance, equipment fabrication, plant construction, acceptance testing, operations planning and training, and the like.

  19. Consistent description of kinetics and hydrodynamics of dusty plasma

    SciTech Connect (OSTI)

    Markiv, B.; Tokarchuk, M.; National University Lviv Polytechnic, 12 Bandera St., 79013 Lviv

    2014-02-15

    A consistent statistical description of kinetics and hydrodynamics of dusty plasma is proposed based on the Zubarev nonequilibrium statistical operator method. For the case of partial dynamics, the nonequilibrium statistical operator and the generalized transport equations for a consistent description of kinetics of dust particles and hydrodynamics of electrons, ions, and neutral atoms are obtained. In the approximation of weakly nonequilibrium process, a spectrum of collective excitations of dusty plasma is investigated in the hydrodynamic limit.

  20. The limits on combining recursive horn rules with description logics

    SciTech Connect (OSTI)

    Levy, A.Y.; Rousset, M.C.

    1996-12-31

    Horn rule languages have formed the basis for many Artificial Intelligence application languages, but are not expressive enough to model domains with a rich hierarchical structure. Description logics have been designed especially to model rich hierarchies. Several applications would significantly benefit from combining the expressive power of both formalisms. This paper focuses on combining recursive function-free Horn rules with the expressive description logic ALCNR, and shows exactly when a hybrid language with decidable inference can be obtained. First, we show that several of the core constructors of description logics lead by themselves to undecidability of inference when combined with recursive function-free Horn rules. We then show that without these constructors we obtain a maximal subset of ALCNRR that yields a decidable hybrid language. Finally, we describe a restriction on the Horn rules that guarantees decidable inference when combined with all of ALCNR, and covers many of the common usages of recursive rules.

  1. Waste receiving and processing plant control system; system design description

    SciTech Connect (OSTI)

    LANE, M.P.

    1999-02-24

    The Plant Control System (PCS) is a heterogeneous computer system composed of numerous sub-systems. The PCS represents every major computer system that is used to support operation of the Waste Receiving and Processing (WRAP) facility. This document, the System Design Description (PCS SDD), includes several chapters and appendices. Each chapter is devoted to a separate PCS sub-system. Typically, each chapter includes an overview description of the system, a list of associated documents related to operation of that system, and a detailed description of relevant system features. Each appendice provides configuration information for selected PCS sub-systems. The appendices are designed as separate sections to assist in maintaining this document due to frequent changes in system configurations. This document is intended to serve as the primary reference for configuration of PCS computer systems. The use of this document is further described in the WRAP System Configuration Management Plan, WMH-350, Section 4.1.

  2. DOE-RL Integrated Safety Management System Program Description

    SciTech Connect (OSTI)

    SHOOP, D.S.

    2000-06-29

    The purpose of this Integrated Safety Management System (ISMS) Program Description (PD) is to describe the U.S. Department of Energy (DOE), Richland Operations Office (RL) ISMS as implemented through the RL Integrated Management System (RIMS). This PD does not impose additional requirements but rather provides an overview describing how various parts of the ISMS fit together. Specific requirements for each of the core functions and guiding principles are established in other implementing processes, procedures, and program descriptions that comprise RIMS. RL is organized to conduct work through operating contracts; therefore, it is extremely difficult to provide an adequate ISMS description that only addresses RL functions. Of necessity, this PD contains some information on contractor processes and procedures which then require RL approval or oversight.

  3. System Advisor Model, SAM 2011.12.2: General Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    System Advisor Model, SAM 2011.12.2: General Description Paul Gilman and Aron Dobos Technical Report NREL/TP-6A20-53437 February 2012 NREL is a national laboratory of the U.S. Department of Energy, Office of Energy Efficiency & Renewable Energy, operated by the Alliance for Sustainable Energy, LLC. National Renewable Energy Laboratory 1617 Cole Boulevard Golden, Colorado 80401 303-275-3000 * www.nrel.gov Contract No. DE-AC36-08GO28308 System Advisor Model, SAM 2011.12.2: General Description

  4. OECD MCCI project 2-D Core Concrete Interaction (CCI) tests : CCI-3 test data report-thermalhydraulic results. Rev. 0 October 15, 2005.

    SciTech Connect (OSTI)

    Farmer, M. T.; Lomperski, S.; Kilsdonk, D. J.; Aeschlimann, R. W.; Basu, S.

    2011-05-23

    kg PWR core melt, initially containing 15 wt% siliceous concrete, with a specially designed two-dimensional siliceous concrete test section with an initial cross-sectional area of 50 cm x 50 cm. The sand and aggregate constituents for this particular siliceous concrete were provided by CEA as an in-kind contribution to the program. The report begins by providing a summary description of the CCI-3 test apparatus and operating procedures, followed by presentation of the thermal-hydraulic results. Detailed posttest debris examination results will be provided in a subsequent publication. Observations drawn within this report regarding the overall cavity erosion behavior may be subject to revision once the posttest examinations are completed, since these examinations will fully reveal the final cavity shape.

  5. OECD MCCI 2-D Core Concrete Interaction (CCI) tests : CCI-2 test data report-thermalhydraulic results, Rev. 0 October 15, 2004.

    SciTech Connect (OSTI)

    Farmer, M. T.; Lomperski, S.; Kilsdonk, D. J.; Aeschlimann, R. W.; Basu, S.

    2011-05-23

    PWR core melt, initially containing 8 wt % Limestone/Common Sand (LCS) concrete, with a specially designed two-dimensional LCS concrete test section with an initial cross-sectional area of 50 cm x 50 cm. The report begins by providing a summary description of the CCI-2 test apparatus and operating procedures, followed by presentation of the thermal-hydraulic results. Detailed posttest debris examination results will be provided in a subsequent publication. Observations drawn within this report regarding the overall cavity erosion behavior may be subject to revision once the posttest examinations are completed, since these examinations will fully reveal the final cavity shape.

  6. OECD MMCI 2-D Core Concrete Interaction (CCI) tests : CCCI-1 test data report-thermalhydraulic results. Rev 0 January 31, 2004.

    SciTech Connect (OSTI)

    Farmer, M. T.; Lomperski, S.; Aeschlimann, R. W.; Basu, S.

    2011-05-23

    PWR core melt, initially containing 8 wt % calcined siliceous concrete, with a specially designed two-dimensional siliceous concrete test section with an initial cross-sectional area of 50 cm x 50 cm. The report begins by providing a summary description of the CCI-1 test apparatus and operating procedures, followed by presentation of the thermal-hydraulic results. The posttest debris examination results will be provided in a subsequent publication. Observations drawn within this report regarding the overall cavity erosion behavior may be subject to revision once the posttest examinations are completed, since these examinations will fully reveal the final cavity shape.

  7. Tank Waste Remediation System (TWRS) Technical Baseline Summary Description

    SciTech Connect (OSTI)

    TEDESCHI, A.R.

    2000-04-21

    This revision notes the supersedure of the subject document by concurrent issuance of HNF-1901 ''Technical Baseline Summary Description for the Tank Farm Contractor'', Revision 2. Safe storage mission technical baseline information was absorbed by the new revision of HNF-1901.

  8. Tank waste remediation system technical baseline summary description

    SciTech Connect (OSTI)

    Raymond, R.E.

    1998-01-08

    This document is one of the tools used to develop and control the mission work as depicted in the included figure. This Technical Baseline Summary Description document is the top-level tool for management of the Technical Baseline for waste storage operations.

  9. A climatological description of the Savannah River Site

    SciTech Connect (OSTI)

    Hunter, C.H.

    1990-05-22

    This report provides a general climatological description of the Savannah River Site. The description provides both regional and local scale climatology. The regional climatology includes a general regional climatic description and presents information on occurrence frequencies of the severe meteorological phenomena that are important considerations in the design and siting of a facility. These phenomena include tornadoes, thunderstorms, hurricanes, and ice/snow storms. Occurrence probabilities given for extreme tornado and non-tornado winds are based on previous site specific studies. Local climatological conditions that are significant with respect to the impact of facility operations on the environment are described using on-site or near-site meteorological data. Summaries of wind speed, wind direction, and atmospheric stability are primarily based on the most recently generated five-year set of data collected from the onsite meteorological tower network (1982--86). Temperature, humidity, and precipitation summaries include data from SRL's standard meteorological instrument shelter and the Augusta National Weather Service office at Bush Field through 1986. A brief description of the onsite meteorological monitoring program is also provided. 24 refs., 15 figs., 22 tabs.

  10. Computer System, Cluster, and Networking Summer Institute Program Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    System, Cluster, and Networking Summer Institute Program Description The Computer System, Cluster, and Networking Summer Institute (CSCNSI) is a focused technical enrichment program targeting third-year college undergraduate students currently engaged in a computer science, computer engineering, or similar major. The program emphasizes practical skill development in setting up, configuring, administering, testing, monitoring, and scheduling computer systems, supercomputer clusters, and computer

  11. SPEAR fuel reliability code system. General description. [PWR; BWR

    SciTech Connect (OSTI)

    Christensen, R.

    1980-03-01

    A general description is presented for the SPEAR fuel reliability code system. Included is a discussion of the methodology employed and the structure of the code system, as well as discussion of the major components: the data preparation routines, the mechanistic fuel performance model, the mechanistic cladding failure model, and the statistical failure model.

  12. Description of recommended non-thermal mixed waste treatment technologies: Version 1.0

    SciTech Connect (OSTI)

    1995-08-01

    This document contains description of the technologies selected for inclusions in the Integrated Nonthermal Treatment Systems (INTS) Study. The purpose of these descriptions is to provide a more complete description of the INTS technologies. It supplements the summary descriptions of candidate nonthermal technologies that were considered for the INTS.

  13. ADDENDUM TO ACTION DESCRIPTION MEMORANDUM NIAGARA FALLS STORAGE SITE

    Office of Legacy Management (LM)

    ADDENDUM TO ACTION DESCRIPTION MEMORANDUM NIAGARA FALLS STORAGE SITE PROPOSED INTERIM REMEDIAL ACTIONS FOR FY 1983-85 ACCELERATED PROGRAM (1984 VICINITY PROPERTIES CLEANUP) Prepared by Environmental Research Division Argonne National Laboratory Argonne, Illinois July 1984 Prepared for U.S. Department of Energy Oak Ridge Operations Technical Services Division Oak Ridge, Tennessee CONTENTS Page SUMMARY OF PROPOSED ACTION AND RELATED ACTIVITIES ........... 1 HISTORY AND ENVIRONMENTAL SETTING

  14. Postdoctoral Program Program Description The Postdoctoral (Postdoc) Research

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Postdoctoral Program Program Description The Postdoctoral (Postdoc) Research program offers the opportunity for appointees to perform research in a robust scientific R&D environment, present and publish research, advance knowledge in basic and applied science, and strengthen national scientific and technical capabilities. Program Mission The Postdoctoral Program provides the opportunity for appointees to perform scientifically rich research, showcase their work through publishing and

  15. Community College Institute (CCI) Program Description The Community College Internship

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Community College Institute (CCI) Program Description The Community College Internship (CCI) program seeks to encourage community college students to enter technical careers relevant to the DOE mission by providing technical training experiences at the DOE laboratories. Selected students participate as interns appointed at one of 15 participating DOE laboratories. They work on technologies or instrumentation projects at major research facilities supporting DOE's mission under the guidance of

  16. Oil-Consumption-Weighted GDP: Description, Calculation, and Comparison

    U.S. Energy Information Administration (EIA) Indexed Site

    Oil-Consumption-Weighted GDP: Description, Calculation, and Comparison Vipin Arora, Tyler Hodge, and Tancred Lidderdale May 2016 Independent Statistics & Analysis www.eia.gov U.S. Energy Information Administration Washington, DC 20585 This paper is released to encourage discussion and critical comment. The analysis and conclusions expressed here are those of the authors and not necessarily those of the U.S. Energy Information Administration. Our thanks to Vinay Tripathi, summer intern from

  17. CATEGORICAL EXCLUSION (CX) DETERMINATION BRIEF DESCRIPTION OF PROPOSED ACTION:

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    'u ", lt~Fs::::N CATEGORICAL EXCLUSION (CX) DETERMINATION BRIEF DESCRIPTION OF PROPOSED ACTION: Southwestern Power Administration proposes to construct a maintenance garage for heavy vehicles and equipment at the Springfield, Missouri facility. PROPOSED BY: Southwestern Power Administration- U.S. Dept. of Energy DATE: December 7,2010 NUMBERS AND TITLES OF THE CATEGORICAL EXCLUSIONS BEING APPLIED: 10 CFR 1021, Appendix B to Subpart D, Part B1.15- Siting, construction or modification of

  18. CATEGORICAL EXCLUSION (CX) DETERMINATION BRIEF DESCRIPTION OF PROPOSED ACTION:

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    CATEGORICAL EXCLUSION (CX) DETERMINATION BRIEF DESCRIPTION OF PROPOSED ACTION: Southwestern Power Administration (Southwestern) proposes to obtain an easement for an existing access road which is located in Carroll County, Arkansas. The easement will serve to facilitate Southwestern's electrical utility vehicles accessing electrical transmission line 3008, near structure 33, in Carroll County, Arkansas. PROPOSED BY: Southwestern Power Administration- U.S. Dept. of Energy DATE: January 28,2011

  19. Task Descriptions | Center for Bio-Inspired Solar Fuel Production

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Task Descriptions Center for Bio-Inspired Solar Fuel Production Central to design of a complete system for solar water oxidation and hydrogen production is incorporation of synthetic components inspired by natural systems into one operational unit. The research effort of the Center is naturally divided into the following subtasks: Subtask 1. Total systems analysis, assembly and testing The solar water splitting device consists of four subsystems, each of which is being investigated by one of the

  20. 2010-12-1-DICE-Diagnostic-Service-Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Editor: Joe Metzger Status: DRAFT (v1.0) Date: 2010-12-1 1 General Service Description for DICE Network Diagnostic Services The DICE collaboration network diagnostic service will simplify the process of debugging, isolating, and correcting multi-domain network performance problems. The diagnostic service will allow users to measure network characteristics across multi-domain network paths. The service is designed to support network engineers in situations where a customer is experiencing

  1. Reducing uncertainty in geostatistical description with well testing pressure data

    SciTech Connect (OSTI)

    Reynolds, A.C.; He, Nanqun; Oliver, D.S.

    1997-08-01

    Geostatistics has proven to be an effective tool for generating realizations of reservoir properties conditioned to static data, e.g., core and log data and geologic knowledge. Due to the lack of closely spaced data in the lateral directions, there will be significant variability in reservoir descriptions generated by geostatistical simulation, i.e., significant uncertainty in the reservoir descriptions. In past work, we have presented procedures based on inverse problem theory for generating reservoir descriptions (rock property fields) conditioned to pressure data and geostatistical information represented as prior means for log-permeability and porosity and variograms. Although we have shown that the incorporation of pressure data reduces the uncertainty below the level contained in the geostatistical model based only on static information (the prior model), our previous results assumed did not explicitly account for uncertainties in the prior means and the parameters defining the variogram model. In this work, we investigate how pressure data can help detect errors in the prior means. If errors in the prior means are large and are not taken into account, realizations conditioned to pressure data represent incorrect samples of the a posteriori probability density function for the rock property fields, whereas, if the uncertainty in the prior mean is incorporated properly into the model, one obtains realistic realizations of the rock property fields.

  2. PROJECT W-551 INTERIM PRETREATMENT SYSTEM PRECONCEPTUAL CANDIDATE TECHNOLOGY DESCRIPTIONS

    SciTech Connect (OSTI)

    MAY TH

    2008-08-12

    The Office of River Protection (ORP) has authorized a study to recommend and select options for interim pretreatment of tank waste and support Waste Treatment Plant (WTP) low activity waste (LAW) operations prior to startup of all the WTP facilities. The Interim Pretreatment System (IPS) is to be a moderately sized system which separates entrained solids and 137Cs from tank waste for an interim time period while WTP high level waste vitrification and pretreatment facilities are completed. This study's objective is to prepare pre-conceptual technology descriptions that expand the technical detail for selected solid and cesium separation technologies. This revision includes information on additional feed tanks.

  3. PBS ABB Title ABB Description/Scope ORP-0014

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Title ABB Description/Scope ORP-0014 242A Evaporator/222-S Laboratory * Operate and maintain the 242-A Evaporator * 222-S Safe and Compliant Operations * 222-S Facililty Reliability * 222-S Analytical Support/Equipment * 222-S Process Chemistry and Waste Handling ORP-0014 A/AX - Farm Retrieval Design, procurement, construction, readiness assessments, start-up, and operations of waste retrieval systems for 241-A and 241-AX Tank Farms. New systems will: 1) retrieve waste from 241-A and 241-AX

  4. 850/sup 0/C VHTR plant technical description

    SciTech Connect (OSTI)

    Not Available

    1980-06-01

    This report describes the conceptual design of an 842-MW(t) process heat very high temperature reactor (VHTR) plant having a core outlet temperature of 850/sup 0/C (1562/sup 0/F). The reactor is a variation of the high-temperature gas-cooled reactor (HTGR) power plant concept. The report includes a description of the nuclear heat source (NHS) and of the balance of reactor plant (BORP) requirements. The design of the associated chemical process plant is not covered in this report. The reactor design is similar to a previously reported VHTR design having a 950/sup 0/C (1742/sup 0/F) core outlet temperature.

  5. System Advisor Model, SAM 2014.1.14: General Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    System Advisor Model, SAM 2014.1.14: General Description Nate Blair, Aron P. Dobos, Janine Freeman, Ty Neises, and Michael Wagner National Renewable Energy Laboratory Tom Ferguson, Paul Gilman, and Steven Janzou Independent Consultants Technical Report NREL/TP-6A20-61019 February 2014 NREL is a national laboratory of the U.S. Department of Energy Office of Energy Efficiency & Renewable Energy Operated by the Alliance for Sustainable Energy, LLC This report is available at no cost from the

  6. About the statistical description of gas-liquid flows

    SciTech Connect (OSTI)

    Sanz, D.; Guido-Lavalle, G.; Carrica, P.

    1995-09-01

    Elements of the probabilistic geometry are used to derive the bubble coalescence term of the statistical description of gas liquid flows. It is shown that the Boltzmann`s hypothesis, that leads to the kinetic theory of dilute gases, is not appropriate for this kind of flows. The resulting integro-differential transport equation is numerically integrated to study the flow development in slender bubble columns. The solution remarkably predicts the transition from bubbly to slug flow pattern. Moreover, a bubbly bimodal size distribution is predicted, which has already been observed experimentally.

  7. Requirements Management System Browser (RMSB) software design description

    SciTech Connect (OSTI)

    Frank, D.D.

    1996-09-30

    The purpose of this document is to provide an ``as-built`` design description for the Requirements Management System Browser (RMSB) application. The Graphical User Interface (GUI) and database structure design are described for the RMSB application, referred to as the ``Browser.`` The RMSB application provides an easy to use PC-based interface to browse systems engineering data stored and managed in a UNIX software application. The system engineering data include functions, requirements, and architectures that make up the Tank Waste Remediation System (TWRS) technical baseline.

  8. Advances in the ab initio description of nuclear three-cluster...

    Office of Scientific and Technical Information (OSTI)

    description of nuclear three-cluster systems Citation Details In-Document Search Title: Advances in the ab initio description of nuclear three-cluster systems Authors: Redondo, C R ...

  9. ALEGRA: User Input and Physics Descriptions Version 4.2 (Technical...

    Office of Scientific and Technical Information (OSTI)

    ALEGRA: User Input and Physics Descriptions Version 4.2 Citation Details In-Document Search Title: ALEGRA: User Input and Physics Descriptions Version 4.2 ALEGRA is an arbitrary ...

  10. ALEGRA: User Input and Physics Descriptions Version 4.2 (Technical...

    Office of Scientific and Technical Information (OSTI)

    ALEGRA: User Input and Physics Descriptions Version 4.2 Citation Details In-Document Search Title: ALEGRA: User Input and Physics Descriptions Version 4.2 You are accessing a ...

  11. Electric Markets Technical Assistance Program: FY2001 Grant Descriptions and Contact Information

    Broader source: Energy.gov [DOE]

    Grant descriptions and contact information for grants awarded under the Electric Markets Technical Assistance Program in FY 2001.

  12. Electric Markets Technical Assistance Program: FY2002 Grant Descriptions and Contact Information

    Broader source: Energy.gov [DOE]

    Grant descriptions and contact information for grants awarded in FY 2002 under the Electric Markets Technical Assistance Program

  13. Electric Markets Technical Assistance Program: FY2003 Grant Descriptions and Contact Information

    Broader source: Energy.gov [DOE]

    Grant descriptions and contact information for grants awarded during FY2003 under the Electric Markets Technical Assistance Program

  14. Descriptions of ESPC Task Order Schedules and Placement of Pricing Information (IDIQ Attachment J-5)

    Broader source: Energy.gov [DOE]

    Document provides task order schedule descriptions and information on the placement of pricing for energy savings performance contracts (ESPCs).

  15. Thermodynamical description of stationary, asymptotically flat solutions with conical singularities

    SciTech Connect (OSTI)

    Herdeiro, Carlos; Rebelo, Carmen; Radu, Eugen

    2010-05-15

    We examine the thermodynamical properties of a number of asymptotically flat, stationary (but not static) solutions having conical singularities, with both connected and nonconnected event horizons, using the thermodynamical description recently proposed in [C. Herdeiro, B. Kleihaus, J. Kunz, and E. Radu, Phys. Rev. D 81, 064013 (2010).]. The examples considered are the double-Kerr solution, the black ring rotating in either S{sup 2} or S{sup 1}, and the black Saturn, where the balance condition is not imposed for the latter two solutions. We show that not only the Bekenstein-Hawking area law is recovered from the thermodynamical description, but also the thermodynamical angular momentum is the Arnowitt-Deser-Misner angular momentum. We also analyze the thermodynamical stability and show that, for all these solutions, either the isothermal moment of inertia or the specific heat at constant angular momentum is negative, at any point in parameter space. Therefore, all these solutions are thermodynamically unstable in the grand canonical ensemble.

  16. Focused Crawling of the Deep Web Using Service Class Descriptions

    SciTech Connect (OSTI)

    Rocco, D; Liu, L; Critchlow, T

    2004-06-21

    Dynamic Web data sources--sometimes known collectively as the Deep Web--increase the utility of the Web by providing intuitive access to data repositories anywhere that Web access is available. Deep Web services provide access to real-time information, like entertainment event listings, or present a Web interface to large databases or other data repositories. Recent studies suggest that the size and growth rate of the dynamic Web greatly exceed that of the static Web, yet dynamic content is often ignored by existing search engine indexers owing to the technical challenges that arise when attempting to search the Deep Web. To address these challenges, we present DynaBot, a service-centric crawler for discovering and clustering Deep Web sources offering dynamic content. DynaBot has three unique characteristics. First, DynaBot utilizes a service class model of the Web implemented through the construction of service class descriptions (SCDs). Second, DynaBot employs a modular, self-tuning system architecture for focused crawling of the DeepWeb using service class descriptions. Third, DynaBot incorporates methods and algorithms for efficient probing of the Deep Web and for discovering and clustering Deep Web sources and services through SCD-based service matching analysis. Our experimental results demonstrate the effectiveness of the service class discovery, probing, and matching algorithms and suggest techniques for efficiently managing service discovery in the face of the immense scale of the Deep Web.

  17. Electric energy supply systems: description of available technologies

    SciTech Connect (OSTI)

    Eisenhauer, J.L.; Rogers, E.A.; King, J.C.; Stegen, G.E.; Dowis, W.J.

    1985-02-01

    When comparing coal transportation with electric transmission as a means of delivering electric power, it is desirable to compare entire energy systems rather than just the transportation/transmission components because the requirements of each option may affect the requirements of other energy system components. PNL's assessment consists of two parts. The first part, which is the subject of this document, is a detailed description of the technical, cost, resource and environmental characteristics of each system component and technologies available for these components. The second part is a computer-based model that PNL has developed to simulate construction and operation of alternative system configurations and to compare the performance of these systems under a variety of economic and technical conditions. This document consists of six chapters and two appendices. A more thorough description of coal-based electric energy systems is presented in the Introduction and Chapter 1. Each of the subsequent chapters describes technologies for five system components: Western coal resources (Chapter 2), coal transportation (Chapter 3), coal gasification and gas transmission (Chapter 4), and electric power transmission (Chapter 6).

  18. Use of seismic attributes in geological description of carbonate rocks

    SciTech Connect (OSTI)

    Castrejon-Vacio, F.; Porres-Luna, A.A.

    1994-12-31

    Seismic attributes have been used widely in order to obtain geological description of petroleum reservoirs, especially as a support for the definition of horizontal continuity of strata, with special emphasis on terrigeneous formations. Nevertheless the application of seismic attributes to the study of carbonate and naturally fractured reservoirs has been limited. This paper shows the application of seismic attributes and seismic inversion to the geological and petrophysical characterization of a naturally fractured reservoir with complex lithology, which is characteristic of the most important producing formations in Mexico. The results from these techniques provide the basis for the definition of a realistic geological model, which is of prime concern for the reservoir`s characterization, numerical studies and EOR applications.

  19. Description of the Portsmouth Gas Centrifuge Enrichment Plant

    SciTech Connect (OSTI)

    Arthur, W.B.

    1980-12-16

    The Portsmouth Gas Centrifuge Enrichment Plant (GCEP) will be located at the site of the Portsmouth Gaseous Diffusion Plant in Piketon, Ohio. The purpose of the facility is to provide enriching services for the production of low assay enriched uranium for civilian nuclear power reactors. The construction and operation of the GCEP is administered by the US Department of Energy. The facility will be operated under contract from the US Government. Control of the GCEP rests solely with the US Government, which holds and controls access to the technology. Construction of GCEP is expected to be completed in the mid-1990's. Many facility design and operating procedures are subject to change. Nonetheless, the design described in this report does reflect current thinking. Descriptions of the general facility and major buildings such as the process buildings, feed and withdrawal building, cylinder storage and transfer, recycle/assembly building, and a summary of the centrifuge uranium enriching process are provided in this report.

  20. San Joaquin-Tulare Conjunctive Use Model: Detailed model description

    SciTech Connect (OSTI)

    Quinn, N.W.T.

    1992-03-01

    The San Joaquin - Tulare Conjunctive Use Model (SANTUCM) was originally developed for the San Joaquin Valley Drainage Program to evaluate possible scenarios for long-term management of drainage and drainage - related problems in the western San Joaquin Valley of California. A unique aspect of this model is its coupling of a surface water delivery and reservoir operations model with a regional groundwater model. The model also performs salinity balances along the tributaries and along the main stem of the San Joaquin River to allow assessment of compliance with State Water Resources Control Board water quality objectives for the San Joaquin River. This document is a detailed description of the various subroutines, variables and parameters used in the model.

  1. Geometry Description Markup Language for Physics Simulation And Analysis Applications.

    SciTech Connect (OSTI)

    Chytracek, R.; McCormick, J.; Pokorski, W.; Santin, G.; /European Space Agency

    2007-01-23

    The Geometry Description Markup Language (GDML) is a specialized XML-based language designed as an application-independent persistent format for describing the geometries of detectors associated with physics measurements. It serves to implement ''geometry trees'' which correspond to the hierarchy of volumes a detector geometry can be composed of, and to allow to identify the position of individual solids, as well as to describe the materials they are made of. Being pure XML, GDML can be universally used, and in particular it can be considered as the format for interchanging geometries among different applications. In this paper we will present the current status of the development of GDML. After having discussed the contents of the latest GDML schema, which is the basic definition of the format, we will concentrate on the GDML processors. We will present the latest implementation of the GDML ''writers'' as well as ''readers'' for either Geant4 [2], [3] or ROOT [4], [10].

  2. Fundamental Statistical Descriptions of Plasma Turbulence in Magnetic Fields

    SciTech Connect (OSTI)

    John A. Krommes

    2001-02-16

    A pedagogical review of the historical development and current status (as of early 2000) of systematic statistical theories of plasma turbulence is undertaken. Emphasis is on conceptual foundations and methodology, not practical applications. Particular attention is paid to equations and formalism appropriate to strongly magnetized, fully ionized plasmas. Extensive reference to the literature on neutral-fluid turbulence is made, but the unique properties and problems of plasmas are emphasized throughout. Discussions are given of quasilinear theory, weak-turbulence theory, resonance-broadening theory, and the clump algorithm. Those are developed independently, then shown to be special cases of the direct-interaction approximation (DIA), which provides a central focus for the article. Various methods of renormalized perturbation theory are described, then unified with the aid of the generating-functional formalism of Martin, Siggia, and Rose. A general expression for the renormalized dielectric function is deduced and discussed in detail. Modern approaches such as decimation and PDF methods are described. Derivations of DIA-based Markovian closures are discussed. The eddy-damped quasinormal Markovian closure is shown to be nonrealizable in the presence of waves, and a new realizable Markovian closure is presented. The test-field model and a realizable modification thereof are also summarized. Numerical solutions of various closures for some plasma-physics paradigms are reviewed. The variational approach to bounds on transport is developed. Miscellaneous topics include Onsager symmetries for turbulence, the interpretation of entropy balances for both kinetic and fluid descriptions, self-organized criticality, statistical interactions between disparate scales, and the roles of both mean and random shear. Appendices are provided on Fourier transform conventions, dimensional and scaling analysis, the derivations of nonlinear gyrokinetic and gyrofluid equations

  3. Nevada Test Site Environmental Report 2008 Attachment A: Site Description

    SciTech Connect (OSTI)

    Cathy A. Wills

    2009-09-01

    This attachment expands on the general description of the Nevada Test Site (NTS) presented in the Introduction to the Nevada Test Site Environmental Report 2008 (National Security Technologies, LLC [NSTec], 2009a). Included are subsections that summarize the sites geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the sites environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site that afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

  4. Nevada Test Site Environmental Report 2009, Attachment A: Site Description

    SciTech Connect (OSTI)

    Cathy Wills, ed.

    2010-09-13

    This attachment expands on the general description of the Nevada Test Site (NTS) presented in the Introduction to the Nevada Test Site Environmental Report 2009. Included are subsections that summarize the sites geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the sites environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site that afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

  5. Nevada Test Site Environmental Report 2005, Attachment A - Site Description

    SciTech Connect (OSTI)

    Cathy A. Wills

    2006-10-01

    This appendix to the ''Nevada Test Site Environmental Report 2005'', dated October 2006 (DOE/NV/11718--1214; DOE/NV/25946--007) expands on the general description of the Nevada Test Site (NTS) presented in the Introduction. Included are subsections that summarize the site?s geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site which afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This appendix complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

  6. Nevada Test Site Environmental Report 2007 Attachment A: Site Description

    SciTech Connect (OSTI)

    Cathy Wills

    2008-09-01

    This appendix expands on the general description of the Nevada Test Site (NTS) presented in the Introduction to the Nevada Test Site Environmental Report 2007 (U.S. Department of Energy [DOE], 2008). Included are subsections that summarize the site's geological, hydrological, climatological, and ecological setting. The cultural resources of the NTS are also presented. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NTS. An adequate knowledge of the site's environment is necessary to assess the environmental impacts of new projects, design and implement environmental monitoring activities for current site operations, and assess the impacts of site operations on the public residing in the vicinity of the NTS. The NTS environment contributes to several key features of the site which afford protection to the inhabitants of adjacent areas from potential exposure to radioactivity or other contaminants resulting from NTS operations. These key features include the general remote location of the NTS, restricted access, extended wind transport times, the great depths to slow-moving groundwater, little or no surface water, and low population density. This attachment complements the annual summary of monitoring program activities and dose assessments presented in the main body of this report.

  7. Reference design description for a geologic repository: Revision 01

    SciTech Connect (OSTI)

    1997-09-01

    This document describes the current design expectations for a potential geologic repository that could be located at Yucca Mountain in Nevada. This Reference Design Description (RDD) looks at the surface and subsurface repository and disposal container design. Additionally, it reviews the expected long-term performance of the potential repository. In accordance with current legislation, the reference design for the potential repository does not include an interim storage option. The reference design presented allows the disposal of highly radioactive material received from government-owned spent fuel custodian sites; produces high-level waste sites, and commercial spent fuel sites. All design elements meet current federal, state, and local regulations governing the disposal of high-level radioactive waste and protection of the public and the environment. Due to the complex nature of developing a repository, the design will be created in three phases to support Viability Assessment, License Application, and construction. This document presents the current reference design. It will be updated periodically as the design progresses. Some of the details presented here may change significantly as more cost-effective solutions, technical advancements, or changes to requirements are identified.

  8. Environmental Compliance and Protection Program Description Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    Bechtel Jacobs

    2009-02-26

    The objective of the Environmental Compliance and Protection (EC and P) Program Description (PD) is to establish minimum environmental compliance requirements and natural resources protection goals for the Bechtel Jacobs Company LLC (BJC) Oak Ridge Environmental Management Cleanup Contract (EMCC) Contract Number DE-AC05-98OR22700-M198. This PD establishes the work practices necessary to ensure protection of the environment during the performance of EMCC work activities on the US Department of Energy's (DOE's) Oak Ridge Reservation (ORR) in Oak Ridge, Tennessee, by BJC employees and subcontractor personnel. Both BJC and subcontractor personnel are required to implement this PD. A majority of the decontamination and demolition (D and D) activities and media (e.g., soil and groundwater) remediation response actions at DOE sites on the ORR are conducted under the authority of the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). CERCLA activities are governed by individual CERCLA decision documents (e.g., Record of Decision [ROD] or Action Memorandum) and according to requirements stated in the Federal Facility Agreement for the Oak Ridge Reservation (DOE 1992). Applicable or relevant and appropriate requirements (ARARs) for the selected remedy are the requirements for environmental remediation responses (e.g., removal actions and remedial actions) conducted under CERCLA.

  9. Two-fluid description of wave-particle interactions in strong...

    Office of Scientific and Technical Information (OSTI)

    Title: Two-fluid description of wave-particle interactions in strong Buneman turbulence To understand the nature of anomalous resistivity in magnetic reconnection, we investigate ...

  10. 2009-01 "Improved Description of Data in the Next Environmental...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    of Data in the Next Environmental Surveillance Report" 2009-01 "Improved Description of Data in the Next Environmental Surveillance Report" The intent of this recommendation ...

  11. Preliminary paper - Development of the Reference Design Description for a geologic repository

    SciTech Connect (OSTI)

    Daniel, Russell B.; Rindskopf, M. Sam

    1997-11-20

    This report describes the current Reference Design Description (RDD) design expectations for a potential geologic repository that could be located at Yucca Mountain in Nevada.

  12. Hong Kong: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Tons NA 2008 EIA Natural Gas Reserves 0 Cubic Meters (cu m) 167 2010 CIA World Factbook Oil Reserves 0 Barrels (bbl) 169 2010 CIA World Factbook Energy Maps featuring Hong Kong...

  13. Norway: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Natural Gas Reserves 2,313,000,000,000 Cubic Meters (cu m) 17 2010 CIA World Factbook Oil Reserves 6,680,000,000 Barrels (bbl) 21 2010 CIA World Factbook Energy Maps featuring...

  14. China: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Natural Gas Reserves 3,030,000,000,000 Cubic Meters (cu m) 13 2010 CIA World Factbook Oil Reserves 20,350,000,000 Barrels (bbl) 13 2010 CIA World Factbook Energy Maps featuring...

  15. Saudi Arabia: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    EIA Natural Gas Reserves 7,461,000,000,000 Cubic Meters (cu m) 5 2010 CIA World Factbook Oil Reserves 264,600,000,000 Barrels (bbl) 1 2010 CIA World Factbook Energy Maps featuring...

  16. Botswana: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Tons 63 2008 EIA Natural Gas Reserves 0 Cubic Meters (cu m) 199 2010 CIA World Factbook Oil Reserves 0 Barrels (bbl) 198 2010 CIA World Factbook Energy Maps featuring Botswana No...

  17. United Kingdom: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    EIA Natural Gas Reserves 292,000,000,000 Cubic Meters (cu m) 40 2010 CIA World Factbook Oil Reserves 3,084,000,000 Barrels (bbl) 31 2010 CIA World Factbook Energy Maps featuring...

  18. Libya: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Natural Gas Reserves 1,539,000,000,000 Cubic Meters (cu m) 23 2010 CIA World Factbook Oil Reserves 47,000,000,000 Barrels (bbl) 9 2010 CIA World Factbook Energy Maps featuring...

  19. Ecuador: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    EIA Natural Gas Reserves 7,985,000,000 Cubic Meters (cu m) 82 2010 CIA World Factbook Oil Reserves 6,542,000,000 Barrels (bbl) 22 2010 CIA World Factbook Energy Maps featuring...

  20. Luxembourg: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Tons NA 2008 EIA Natural Gas Reserves 0 Cubic Meters (cu m) 165 2010 CIA World Factbook Oil Reserves 0 Barrels (bbl) 145 2010 CIA World Factbook Energy Maps featuring Luxembourg...

  1. Trinidad and Tobago: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    EIA Natural Gas Reserves 436,100,000,000 Cubic Meters (cu m) 33 2010 CIA World Factbook Oil Reserves 728,300,000 Barrels (bbl) 42 2010 CIA World Factbook Energy Maps featuring...

  2. Ukraine: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Natural Gas Reserves 1,104,000,000,000 Cubic Meters (cu m) 25 2010 CIA World Factbook Oil Reserves 395,000,000 Barrels (bbl) 53 2010 CIA World Factbook Energy Maps featuring...

  3. Czech Republic: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    EIA Natural Gas Reserves 3,072,000,000 Cubic Meters (cu m) 92 2010 CIA World Factbook Oil Reserves 15,000,000 Barrels (bbl) 86 2010 CIA World Factbook Energy Maps featuring...

  4. Timor-Leste: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    EIA Natural Gas Reserves 200,000,000,000 Cubic Meters (cu m) 45 2010 CIA World Factbook Oil Reserves 553,800,000 Barrels (bbl) 46 2010 CIA World Factbook Energy Maps featuring...

  5. Kyrgyzstan: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    EIA Natural Gas Reserves 5,663,000,000 Cubic Meters (cu m) 91 2010 CIA World Factbook Oil Reserves 40,000,000 Barrels (bbl) 80 2010 CIA World Factbook Energy Maps featuring...

  6. Zambia: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Tons 69 2008 EIA Natural Gas Reserves 0 Cubic Meters (cu m) 118 2010 CIA World Factbook Oil Reserves 0 Barrels (bbl) 105 2010 CIA World Factbook Energy Maps featuring Zambia No...

  7. Sri Lanka: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Tons NA 2008 EIA Natural Gas Reserves 0 Cubic Meters (cu m) 131 2010 CIA World Factbook Oil Reserves 0 Barrels (bbl) 118 2010 CIA World Factbook Energy Maps featuring Sri Lanka...

  8. United States: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    EIA Natural Gas Reserves 6,928,000,000,000 Cubic Meters (cu m) 6 2010 CIA World Factbook Oil Reserves 19,120,000,000 Barrels (bbl) 14 2010 CIA World Factbook Energy Maps featuring...

  9. Puerto Rico: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Tons NA 2008 EIA Natural Gas Reserves 0 Cubic Meters (cu m) 144 2010 CIA World Factbook Oil Reserves 0 Barrels (bbl) 134 2010 CIA World Factbook Energy Maps featuring Puerto Rico...

  10. Niger: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Tons 59 2008 EIA Natural Gas Reserves 0 Cubic Meters (cu m) 149 2010 CIA World Factbook Oil Reserves 0 Barrels (bbl) 148 2010 CIA World Factbook Energy Maps featuring Niger No...

  11. Papua New Guinea: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    EIA Natural Gas Reserves 226,500,000,000 Cubic Meters (cu m) 44 2010 CIA World Factbook Oil Reserves 170,000,000 Barrels (bbl) 62 2010 CIA World Factbook Energy Maps featuring...

  12. Serbia: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    EIA Natural Gas Reserves 48,140,000,000 Cubic Meters (cu m) 66 2010 CIA World Factbook Oil Reserves 77,500,000 Barrels (bbl) 75 2010 CIA World Factbook Energy Maps featuring...

  13. Bosnia and Herzegovina: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Tons 17 2008 EIA Natural Gas Reserves 0 Cubic Meters (cu m) 106 2010 CIA World Factbook Oil Reserves 0 Barrels (bbl) 102 2010 CIA World Factbook Energy Maps featuring Bosnia and...

  14. Malta: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Tons NA 2008 EIA Natural Gas Reserves 0 Cubic Meters (cu m) 113 2010 CIA World Factbook Oil Reserves 0 Barrels (bbl) 138 2010 CIA World Factbook Energy Maps featuring Malta Malta...

  15. Validity of ELTB Equation for Suitable Description of BEC

    SciTech Connect (OSTI)

    Kim, Dooyoung; Kim, Jinguanghao; Yoon, Jin-Hee

    2005-10-17

    The Bose-Einstein condensation (BEC) has been found for various alkali-metal gases such as 7Li, 87Rb, Na, and H. For the description of atoms in this condensate state, the Gross-Pitaevskii (GP) equation has been widely used. However, the GP equation contains the nonlinear term, which makes this equation hard to solve. Therefore, physical quantities are usually obtained numerically, and sometimes it is difficult to extract a physical meaning from the calculated results. The nuclear theory group at Purdue University in the U.S. developed a new simple equation, the equivalent linear two-body (ELTB) equation, using the hyper-radius coordinates and tested it for one-dimensional BEC system. Their results are consistent with the numerical values from the GP equation within 4.5%.We test the validity of the ELTB equation for three-dimensional BEC system by calculating the energies per particle and the wave functions for 87Rb gas and for 7Li gas. We use the quantum-mechanical variational method for the BEC energy. Our result for 87Rb gas agrees with a numerical calculation based on the GP equation, with a relative error of 12% over a wide range of N from 100 to 10,000. The relative distances between particles for 7Li gas are consistent within a relative error of 17% for N {<=} 1300. The relatively simple form of the ELTB equation, compared with the GP equation, enables us to treat the N-body system easily and efficiently. We conclude that the ELTB equation is a powerful equation for describing BEC system because it is easy to treat.

  16. Functional description for the Worldwide Port System (WPS) Regional Integrated Cargo Database (ICDB)

    SciTech Connect (OSTI)

    Truett, L.F.; Rollow, J.P.; Shipe, P.C.; Faby, E.Z.; Fluker, J.; Hancock, W.R.; Grubb, J.W.; Russell, D.L.; Ferguson, R.A.

    1995-12-15

    This Functional Description for the Worldwide Port System (WPS) Regional Integrated Cargo Database (ICDB) documents the purpose of and requirements for the ICDB in order to ensure a mutual understanding between the development group and the user group of the system. This Functional Description defines ICDB and provides a clear statement of the initial operational capability to be developed.

  17. Computer software design description for the integrated control and data acquisition system LDUA system

    SciTech Connect (OSTI)

    Aftanas, B.L.

    1998-08-12

    This Computer Software Design Description (CSDD) document provides the overview of the software design for all the software that is part of the integrated control and data acquisition system of the Light Duty Utility Arm System (LDUA). It describes the major software components and how they interface. It also references the documents that contain the detailed design description of the components.

  18. Description of Transmutation Library for Fuel Cycle System Analyses

    SciTech Connect (OSTI)

    Steven J. Piet; Samuel E. Bays; Edward A. Hoffman

    2010-08-01

    This report documents the Transmutation Library that is used in Fuel Cycle System Analyses. This version replaces the 2008 version.[Piet2008] The Transmutation Library has the following objectives: • Assemble past and future transmutation cases for system analyses. • For each case, assemble descriptive information such as where the case was documented, the purpose of the calculation, the codes used, source of feed material, transmutation parameters, and the name of files that contain raw or source data. • Group chemical elements so that masses in separation and waste processes as calculated in dynamic simulations or spreadsheets reflect current thinking of those processes. For example, the CsSr waste form option actually includes all Group 1A and 2A elements. • Provide mass fractions at input (charge) and output (discharge) for each case. • Eliminate the need for either “fission product other” or “actinide other” while conserving mass. Assessments of waste and separation cannot use “fission product other” or “actinide other” as their chemical behavior is undefined. • Catalog other isotope-specific information in one place, e.g., heat and dose conversion factors for individual isotopes. • Describe the correlations for how input and output compositions change as a function of UOX burnup (for LWR UOX fuel) or fast reactor (FR) transuranic (TRU) conversion ratio (CR) for either FR-metal or FR-oxide. This document therefore includes the following sections: • Explanation of the data set information, i.e., the data that describes each case. In no case are all of the data presented in the Library included in previous documents. In assembling the Library, we return to raw data files to extract the case and isotopic data, into the specified format. • Explanation of which isotopes and elements are tracked. For example, the transition metals are tracked via the following: two Zr isotopes, Zr-other, Tc99, Tc-other, two Mo-Ru-Rh-Pd isotopes, Mo

  19. Baseline Concept Description of a Small Modular High Temperature Reactor

    SciTech Connect (OSTI)

    Hans Gougar

    2014-05-01

    The objective of this report is to provide a description of generic small modular high temperature reactors (herein denoted as an smHTR), summarize their distinguishing attributes, and lay out the research and development (R&D) required for commercialization. The generic concepts rely heavily on the modular high temperature gas-cooled reactor designs developed in the 1980s which were never built but for which pre-licensing or certification activities were conducted. The concept matured more recently under the Next Generation Nuclear Plant (NGNP) project, specifically in the areas of fuel and material qualification, methods development, and licensing. As all vendor-specific designs proposed under NGNP were all both ‘small’ or medium-sized and ‘modular’ by International Atomic Energy Agency (IAEA) and Department of Energy (DOE) standards, the technical attributes, challenges, and R&D needs identified, addressed, and documented under NGNP are valid and appropriate in the context of Small Modular Reactor (SMR) applications. Although the term High Temperature Reactor (HTR) is commonly used to denote graphite-moderated, thermal spectrum reactors with coolant temperatures in excess of 650oC at the core outlet, in this report the historical term High Temperature Gas-Cooled Reactor (HTGR) will be used to distinguish the gas-cooled technology described herein from its liquid salt-cooled cousin. Moreover, in this report it is to be understood that the outlet temperature of the helium in an HTGR has an upper limit of 950 degrees C which corresponds to the temperature to which certain alloys are currently being qualified under DOE’s ARC program. Although similar to the HTGR in just about every respect, the Very High Temperature Reactor (VHTR) may have an outlet temperature in excess of 950 degrees C and is therefore farther from commercialization because of the challenges posed to materials exposed to these temperatures. The VHTR is the focus of R&D under the

  20. Baseline Concept Description of a Small Modular High Temperature Reactor

    SciTech Connect (OSTI)

    Gougar, Hans D.

    2014-10-01

    The objective of this report is to provide a description of generic small modular high temperature reactors (herein denoted as an smHTR), summarize their distinguishing attributes, and lay out the research and development (R&D) required for commercialization. The generic concepts rely heavily on the modular high temperature gas-cooled reactor designs developed in the 1980s which were never built but for which pre-licensing or certification activities were conducted. The concept matured more recently under the Next Generation Nuclear Plant (NGNP) project, specifically in the areas of fuel and material qualification, methods development, and licensing. As all vendor-specific designs proposed under NGNP were all both ‘small’ or medium-sized and ‘modular’ by International Atomic Energy Agency (IAEA) and Department of Energy (DOE) standards, the technical attributes, challenges, and R&D needs identified, addressed, and documented under NGNP are valid and appropriate in the context of Small Modular Reactor (SMR) applications. Although the term High Temperature Reactor (HTR) is commonly used to denote graphite-moderated, thermal spectrum reactors with coolant temperatures in excess of 650oC at the core outlet, in this report the historical term High Temperature Gas-Cooled Reactor (HTGR) will be used to distinguish the gas-cooled technology described herein from its liquid salt-cooled cousin. Moreover, in this report it is to be understood that the outlet temperature of the helium in an HTGR has an upper limit of 950 degrees C which corresponds to the temperature to which certain alloys are currently being qualified under DOE’s ARC program. Although similar to the HTGR in just about every respect, the Very High Temperature Reactor (VHTR) may have an outlet temperature in excess of 950 degrees C and is therefore farther from commercialization because of the challenges posed to materials exposed to these temperatures. The VHTR is the focus of R&D under the

  1. Baseline Concept Description of a Small Modular High Temperature Reactor

    SciTech Connect (OSTI)

    Hans Gougar

    2014-05-01

    The objective of this report is to provide a description of generic small modular high temperature reactors (herein denoted as an smHTR), summarize their distinguishing attributes, and lay out the research and development (R&D) required for commercialization. The generic concepts rely heavily on the modular high temperature gas-cooled reactor designs developed in the 1980s which were never built but for which pre-licensing or certification activities were conducted. The concept matured more recently under the Next Generation Nuclear Plant (NGNP) project, specifically in the areas of fuel and material qualification, methods development, and licensing. As all vendor-specific designs proposed under NGNP were all both small or medium-sized and modular by International Atomic Energy Agency (IAEA) and Department of Energy (DOE) standards, the technical attributes, challenges, and R&D needs identified, addressed, and documented under NGNP are valid and appropriate in the context of Small Modular Reactor (SMR) applications. Although the term High Temperature Reactor (HTR) is commonly used to denote graphite-moderated, thermal spectrum reactors with coolant temperatures in excess of 650oC at the core outlet, in this report the historical term High Temperature Gas-Cooled Reactor (HTGR) will be used to distinguish the gas-cooled technology described herein from its liquid salt-cooled cousin. Moreover, in this report it is to be understood that the outlet temperature of the helium in an HTGR has an upper limit of 950 degrees C which corresponds to the temperature to which certain alloys are currently being qualified under DOEs ARC program. Although similar to the HTGR in just about every respect, the Very High Temperature Reactor (VHTR) may have an outlet temperature in excess of 950 degrees C and is therefore farther from commercialization because of the challenges posed to materials exposed to these temperatures. The VHTR is the focus of R&D under the Generation IV

  2. RELAP5 Model Description and Validation for the BR2 Loss-of-Flow Experiments

    SciTech Connect (OSTI)

    Licht, J. R.; Dionne, B.; Van den Branden, G.; Sikik, E.; Koonen, E.

    2015-07-01

    This paper presents a description of the RELAP5 model, the calibration method used to obtain the minor loss coefficients from the available hydraulic data and the LOFA simulation results compared to the 1963 experimental tests for HEU fuel.

  3. ORISE Contract, PART I … THE SCHEDULE, Section C Description/Specifications/Work Statement

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    PART I - THE SCHEDULE SECTION C DESCRIPTION/SPECIFICATIONS/WORK STATEMENT C.1 PERFORMANCE WORK STATEMENT (NOV 2004) ................................................... 3 1.0 SCOPE............................................................................................................................... 3 2.0 PERFORMANCE WORK STATEMENT OBJECTIVES .......................................... 4 3.0 RELATED SERVICES (NOV 2004)

  4. Health, Safety & Environment System Description and Worker Safety & Health Program

    National Nuclear Security Administration (NNSA)

    FY2015 HEALTH, SAFETY AND ENVIRONMENT MANAGEMENT SYSTEM DESCRIPTION and WORKER SAFETY & HEALTH PROGRAM Honeywell Federal Manufacturing & Technologies HS&E Management System Description 1 Honeywell Approval: KCFO Approval: Original Signed by Don Fitzpatrick 8/27/14 Original Signed by Sherry Kinsey-Cannon 8/27/14 Donald J. Fitzpatrick, Director Date Sherry Kinsey-Cannon, Date HSE&F Acting Assistant Manager Office of Operations KCFO Worker Safety & Health Program 2 Honeywell

  5. NAICS Codes @ Headquarters Description: NAICS Codes used at Headquarters Procurement Services

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    NAICS Codes @ Headquarters Description: NAICS Codes used at Headquarters Procurement Services Filters: Signed Date only show values between , Contracting Agency ID show only ('8900'), Contracting Office ID show only ('00001'), Date Signed only show values between '05/01/2011' and '04/30/2012', Last Modified Date only show values between Contracting Agency ID: 8900, Contracting Office ID: 00001 NAICS Code NAICS Description Action Obligation 541519 OTHER COMPUTER RELATED SERVICES 341

  6. 2009-01 "Improved Description of Data in the Next Environmental

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Surveillance Report" | Department of Energy 1 "Improved Description of Data in the Next Environmental Surveillance Report" 2009-01 "Improved Description of Data in the Next Environmental Surveillance Report" The intent of this recommendation is to aid the DOE and LANL in their efforts to keep the general public fully informed of the ongoing cleanup. Rec 2009-01 - January 28, 2009 (19.7

  7. Program Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    It is held in conjunction with National Engineers Week which is celebrated at the time of George Washington's birthday, our nation's first President, who was a military engineer ...

  8. Program Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    The Los Alamos STEM Challenge gives your students a unique opportunity to envision the future years of discovery at LANL. Students will develop 21st century skills as they collaborate in teams to research LANL projects and propose innovative future projects. They apply creativity and critical thinking skills as they visualize their own ideas through posters, videos, apps or essays describing potential future projects at LANL. Students are encouraged to learn about the Laboratory via the contest

  9. Partnership Description

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Department of Energy (DOE) is establishing a voluntary partnership program, the Partnership for Energy Sector Climate Resilience (Partnership), between energy companies and DOE. The focus of this Partnership will be to enhance energy security by collaborating with the private sector to establish a 21st century energy system resilient to extreme weather and climate change.

  10. Program Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Applied Geophysical Experience, is a unique educational program designed to introduce students in geophysics and related fields to "hands on" geophysical exploration and research....

  11. Program Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    their potential and pursue opportunities in science, technology, engineering and mathematics. Through Expanding Your Horizon (EYH) Network programs, we provide STEM role models...

  12. Program Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    of MATHCOUNTS is to increase enthusiasm for and enhance achievement in middle school mathematics throughout the United States. MATHCOUNTS is supported by the National Society of...

  13. Program Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    academic competition that tests students' knowledge in all areas of science and mathematics. Middle and high school student teams from diverse backgrounds are comprised of...

  14. EMS Description

    Broader source: Energy.gov [DOE]

    This document describes the joint U.S. Department of Energy (DOE) Office of Legacy Management (LM) and the Legacy Management Support (LMS) Contractor Team Environmental Management System (EMS).

  15. Program Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    LANL projects and propose innovative future projects. They apply creativity and critical thinking skills as they visualize their own ideas through posters, videos, apps or essays...

  16. Program Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    E (Engineering) is an evening of interesting, interactive and fun engineering, science, math, and technology demonstrations for K-12 students and their parents or guardians. It is...

  17. Program Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    competition that tests students' knowledge in all areas of science and mathematics. ... students to excel in mathematics and science and to pursue careers in these fields. ...

  18. Program Description

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    mathematics throughout the United States. MATHCOUNTS is supported by the National Society of Professional Engineers (NSPE), The National Council of Teachers of Mathematics and ...

  19. Engineer/constructor description of work for Tank 241-SY-102 retrieval system, project W-211, initial tank retrieval systems

    SciTech Connect (OSTI)

    Rieck, C.A.

    1996-02-01

    This document provides a description of work for the design and construction of a waste retrieval system for Tank 241-SY-102. The description of work includes a working estimate and schedule, as well as a narrative description and sketches of the waste retrieval system. The working estimate and schedule are within the established baselines for the Tank 241-SY-102 retrieval system. The technical baseline is provided in Functional Design Criteria, WHC-SD-W211-FDC-001, Revision 2.

  20. TPX: Contractor preliminary design review. Volume 1, Presentation and design description. Final report

    SciTech Connect (OSTI)

    Hartman, D.; Naumovich,; Walstrom, P.; Clarkson, I.; Schultheiss, J.; Burger, A.

    1995-09-22

    This first volume of the five volume set begins with a CPDR overview and then details the PF magnet system, manufacturing R&D, Westinghouse R&D, the central solenoid, the PF 5 ring coil, the PF 6/7 ring coil, quality assurance, and the system design description.

  1. Alternative descriptions of catalyst deactivation in aromatization of propane and butane

    SciTech Connect (OSTI)

    Koshelev, Yu.N.; Vorob`ev, B.L.; Khvorova, E.P.

    1995-08-20

    Deactivation of a zeolite-containing catalyst has been studied in aromatization of propane and butane. Various descriptions of the dependence of the alkane conversion on the coke concentration on the catalyst have been considered, and using a statistical method of estimating the model validity, the most preferable form of the deactivation function has been proposed.

  2. SPEAR-BETA fuel performance code system. Volume 1. General description. Final report. [BWR; PWR

    SciTech Connect (OSTI)

    Christensen, R.

    1982-04-01

    This document provides a general description of the SPEAR-BETA fuel reliability code system. Included is a discussion of the methodology employed and the structure of the code system, as well as discussion of the major components: the data preparation routines, the mechanistic fuel performance model, the mechanistic cladding failure model, and the statistical failure model.

  3. Implementation of a hybrid particle code with a PIC description in r–z and a gridless description in ϕ into OSIRIS

    SciTech Connect (OSTI)

    Davidson, A.; Tableman, A.; An, W.; Tsung, F.S.; Lu, W.; Vieira, J.; Silva, L.O.

    2015-01-15

    For many plasma physics problems, three-dimensional and kinetic effects are very important. However, such simulations are very computationally intensive. Fortunately, there is a class of problems for which there is nearly azimuthal symmetry and the dominant three-dimensional physics is captured by the inclusion of only a few azimuthal harmonics. Recently, it was proposed [1] to model one such problem, laser wakefield acceleration, by expanding the fields and currents in azimuthal harmonics and truncating the expansion. The complex amplitudes of the fundamental and first harmonic for the fields were solved on an r–z grid and a procedure for calculating the complex current amplitudes for each particle based on its motion in Cartesian geometry was presented using a Marder's correction to maintain the validity of Gauss's law. In this paper, we describe an implementation of this algorithm into OSIRIS using a rigorous charge conserving current deposition method to maintain the validity of Gauss's law. We show that this algorithm is a hybrid method which uses a particles-in-cell description in r–z and a gridless description in ϕ. We include the ability to keep an arbitrary number of harmonics and higher order particle shapes. Examples for laser wakefield acceleration, plasma wakefield acceleration, and beam loading are also presented and directions for future work are discussed.

  4. Spent nuclear fuel project cold vacuum drying facility vacuum and purge system design description

    SciTech Connect (OSTI)

    IRWIN, J.J.

    1998-11-30

    This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Vacuum and Purge System (VPS) . The SDD was developed in conjunction with HNF-SD-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-002, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the VPS equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SDD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

  5. Microscopic description of the pygmy dipole resonance and its contribution to radiative capture

    SciTech Connect (OSTI)

    Avdeyenkov, A.; Goriely, S.; Kamerdzhiev, S.; Tertychny, G.

    2009-01-28

    The radiative capture cross sections for the compound nuclei {sup 100}Sn, {sup 132}Sn and {sup 144}Nd have been calculated using both self-consistent and non-selfconsistent microscopic theories which, in addition to the standard RPA or QRPA approaches, take the single-particle continuum and phonon coupling into account. We show that the inclusion of the phonon coupling is necessary for a proper description of the pygmy resonance. Consequently, the radiative capture cross sections and corresponding rates are increased by a factor of 2-3 as compared with RPA or QRPA approaches. We conclude that the present approach provides a more complete and coherent description of the {gamma}-ray strength function than the previous models used so far and for astrophysics applications in particular, such calculations are highly recommended for a more reliable estimate of the electromagnetic properties of exotic nuclei.

  6. System Description for the KW Basin Integrated Water Treatment System (IWTS) (70.3)

    SciTech Connect (OSTI)

    DERUSSEAU, R.R.

    2000-04-18

    This is a description of the system that collects and processes the sludge and radioactive ions released by the spent nuclear fuel (SNF) processing operations conducted in the 105 KW Basin. The system screens, settles, filters, and conditions the basin water for reuse. Sludge and most radioactive ions are removed before the water is distributed back to the basin pool. This system is part of the Spent Nuclear Fuel Project (SNFP).

  7. HQ State HQ City Name of Primary Selectee Project Type Project Title and Brief Project Description

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Name of Primary Selectee Project Type Project Title and Brief Project Description Project Locations Recovery Act Funding* Participant Share Total Project Value Including Cost Share AZ Fort Defiance Navajo Tribal Utility Authority Company Smart Grid Workforce Training (Topic B) Navajo Tribal Utility Authority Smart Grid Workforce Training Program - Develop a workforce that is well-trained and committed to the mission of modernizing NTUA's distribution services, including an expeditious and

  8. Resolving the biophysics of axon transmembrane polarization in a single closed-form description

    SciTech Connect (OSTI)

    Melendy, Robert F.

    2015-12-28

    When a depolarizing event occurs across a cell membrane there is a remarkable change in its electrical properties. A complete depolarization event produces a considerably rapid increase in voltage that propagates longitudinally along the axon and is accompanied by changes in axial conductance. A dynamically changing magnetic field is associated with the passage of the action potential down the axon. Over 75 years of research has gone into the quantification of this phenomenon. To date, no unified model exist that resolves transmembrane polarization in a closed-form description. Here, a simple but formative description of propagated signaling phenomena in the membrane of an axon is presented in closed-form. The focus is on using both biophysics and mathematical methods for elucidating the fundamental mechanisms governing transmembrane polarization. The results presented demonstrate how to resolve electromagnetic and thermodynamic factors that govern transmembrane potential. Computational results are supported by well-established quantitative descriptions of propagated signaling phenomena in the membrane of an axon. The findings demonstrate how intracellular conductance, the thermodynamics of magnetization, and current modulation function together in generating an action potential in a unified closed-form description. The work presented in this paper provides compelling evidence that three basic factors contribute to the propagated signaling in the membrane of an axon. It is anticipated this work will compel those in biophysics, physical biology, and in the computational neurosciences to probe deeper into the classical and quantum features of membrane magnetization and signaling. It is hoped that subsequent investigations of this sort will be advanced by the computational features of this model without having to resort to numerical methods of analysis.

  9. New Mexico Hydrogen Fuels Challenge Program Description The New Mexico Hydrogen Fuels

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    New Mexico Hydrogen Fuels Challenge Program Description The New Mexico Hydrogen Fuels Challenge is an event that provides a hands-on opportunity for middle school students (grades six through eight) to understand the need for renewable energy sources and explore the emerging technology of hydrogen power. It is also an opportunity to engage the future generation of engineers and scientists. Los Alamos National Laboratory is a co-sponsor of the annual regional event along with the Public Service

  10. Descriptions of selected accidents that have occurred at nuclear reactor facilities

    SciTech Connect (OSTI)

    Bertini, H.W.

    1980-04-01

    This report was prepared at the request of the President's Commission on the Accident at Three Mile Island to provide the members of the Commission with some insight into the nature and significance of accidents that have occurred at nuclear reactor facilities in the past. Toward that end, this report presents a brief description of 44 accidents which have occurred throughout the world and which meet at least one of the severity criteria that were established.

  11. Subsurface Conditions Description of the B and BX and BY Waste Management Area

    SciTech Connect (OSTI)

    WOOD, M.I.

    2000-03-13

    This document provides a discussion of the subsurface conditions relevant to the occurrence and migration of contaminants in the vadose zone and groundwater underlying the 241-B, -BX, and -BY tank farms. This document provides a concise summary of existing information in support of characterization planning. This document includes a description of the available environmental contamination data and a limited, qualitative interpretation of these data.

  12. System Design Description and Requirements for Modeling the Off-Gas Systems for Fuel Recycling Facilities

    SciTech Connect (OSTI)

    Daryl R. Haefner; Jack D. Law; Troy J. Tranter

    2010-08-01

    This document provides descriptions of the off-gases evolved during spent nuclear fuel processing and the systems used to capture the gases of concern. Two reprocessing techniques are discussed, namely aqueous separations and electrochemical (pyrochemical) processing. The unit operations associated with each process are described in enough detail so that computer models to mimic their behavior can be developed. The document also lists the general requirements for the desired computer models.

  13. Simple description of light W, Os, and Pt nuclei in the interacting boson model

    SciTech Connect (OSTI)

    McCutchan, E.A.; Zamfir, N.V.

    2005-05-01

    A simple, two-parameter IBA-1 Hamiltonian is applied to light W, Os, and Pt nuclei with N {<=} 104. Equal emphasis is placed on fitting all low-lying positive parity excitations resulting in a good description of energy levels and electromagnetic transition rates. A mapping of these parameters into the IBA symmetry triangle finds that these nuclei lie rather central in the triangle and close to the phase transition region of the IBA model.

  14. System requirements and design description for the environmental requirements management interface (ERMI)

    SciTech Connect (OSTI)

    Biebesheimer, E.

    1997-09-30

    This document describes system requirements and the design description for the Environmental Requirements Management Interface (ERMI). The ERMI database assists Tank Farm personnel with scheduling, planning, and documenting procedure compliance, performance verification, and selected corrective action tracking activities for Tank Farm S/RID requirements. The ERMI database was developed by Science Applications International Corporation (SAIC). This document was prepared by SAIC and edited by LMHC.

  15. SustainX Inc Isothermal Compressed Air Energy Storage Project Description

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    SustainX Inc Isothermal Compressed Air Energy Storage Project Description SustainX is developing and demonstrating a modular, market-ready energy storage system that uses compressed air as the storage medium. SustainX uses a crankshaft-based drivetrain to convert electrical energy into potential energy stored as compressed air. SustainX's ICAES system captures the heat from compression in water and stores the captured heat until it is needed again for expansion. Storing the captured heat

  16. Microsoft Word - 1-SiteDescription Cover DisclaimerTitle Final.doc

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Attachment A: Site Description Northern Harrier (Circus cyaneus) DOE/NV/25946--259 September 2007 Disclaimer Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof or its contractors or subcontractors. Available for sale to the public from: U.S. Department of Commerce National Technical

  17. Microsoft Word - Attach_A_Site Description 2007_Final.doc

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    2007 Attachment A: Site Description DOE/NV/25946--543-ATT-A Vision * Service * Partnership National Security Technologies LLC Schooner Crater September 2008 Disclaimer Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. Available for sale to the public from: U.S. Department of

  18. A correlation between soil descriptions and {sup 226}Ra concentrations in Florida soils

    SciTech Connect (OSTI)

    Harrison, D.P.

    1992-12-31

    The soil radium content in Florida is highly variable. The range in radium concentrations, where the samples involved in this study are concerned, is from 0.1 pCi/g to 18.5 pCi/g. Low {sup 226}Ra concentrations (0.1 to 5 pCi/g) are evidenced in sands, moderate concentrations (5 to 11 pCi/g) are found in silt and gravel, and high {sup 226}Ra concentrations (>11 pCi/g) are found in soil horizons with shell, clay, and strata with phosphate. Strata containing phosphate yields a high concentration of {sup 226}Ra. The information obtained in this study, soil descriptions with their corresponding {sup 226}Ra concentrations, comes from geological cores drilled by geotechnical consultants with gamma spectrometry analysis performed by high resolution gamma spectroscopy. Concentration; of {sup 226}Ra generally increase with depth. These cores are usually terminated at 20 feet deep, with some cores being shallower than this due to hitting bedrock or encountering the water table. These frequency distributions give the core-logging geologist an approximate concentration of {sup 226}Ra based on the description of the soil. Since the correlation of {sup 226}Ra and soil descriptions can be used as a tool in assigning indoor radon potential, this study is of importance to land managers, contractors, developers, and regulating agencies who are attempting to place standards on tracts of land with {sup 226}Ra concentration used as a criterion.

  19. Two-band description of resonant superfluidity in atomic Fermi gases

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    He, Lianyi; Hu, Hui; Liu, Xia -Ji

    2015-02-23

    Fermionic superfluidity in atomic Fermi gases across a Feshbach resonance is normally described by the atom-molecule theory, which treats the closed channel as a noninteracting point boson. In this work we present a theoretical description of the resonant superfluidity in analogy to the two-band superconductors. We employ the underlying two-channel scattering model of Feshbach resonance where the closed channel is treated as a composite boson with binding energy ε0 and the resonance is triggered by the microscopic interchannel coupling U12. The binding energy ε0 naturally serves as an energy scale of the system, which has been sent to infinity inmore » the atom-molecule theory. We show that the atom-molecule theory can be viewed as a leading-order low-energy effective theory of the underlying fermionic theory in the limit ε0→∞ and U12→0, while keeping the phenomenological atom-molecule coupling finite. The resulting two-band description of the superfluid state is in analogy to the BCS theory of two-band superconductors. In the dilute limit ε0→∞, the two-band description recovers precisely the atom-molecule theory. The two-band theory provides a natural approach to study the corrections because of a finite binding energy ε0 in realistic experimental systems. For broad and moderate resonances, the correction is not important for current experimental densities. However, for extremely narrow resonance, we find that the correction becomes significant. Lastly, the finite binding energy correction could be important for the stability of homogeneous polarized superfluid against phase separation in imbalanced Fermi gases across a narrow Feshbach resonance.« less

  20. Shell Model Description of the Odd-Odd Co and Cu Nuclei

    SciTech Connect (OSTI)

    Medina, N. H.; Allegro, P. R. P.; Oliveira, J. R. B. de; Ribas, R. V.; Seale, W. A.; Toufen, D. L.; Silveira, M. A. G.

    2007-10-26

    The known excited states of the odd-odd nuclei {sup 54,56,58,60}Co and 60,62,64,66Cu were interpreted in the framework of the large scale shell model (LSSM), using several effective interactions and configuration spaces. For the description of the negative parity states, we have allowed one particle excitation to the g{sub 9/2} orbital. The LSSM using the GXPF1 effective interaction reproduces well the first excited states in all of these nuclei.

  1. Spent nuclear fuel technical baseline description, Fiscal Year 1996: Volume II, supporting data

    SciTech Connect (OSTI)

    Womack, J.C.

    1995-11-01

    The Technical Baseline Description documents the Project-Level functions and requirements, along with associated enabling assumptions, issues, trade studies, interfaces, and products. It is a snapshot in time of the baseline at the beginning of September 1995. It supports the individual subprojects in the development of lower-tier functions, requirements, and specifications in FY 1996. It also supports the need for Hanford site planning to be based on an integrated Hanford site systems engineering technical baseline; and is traceable to that baseline. This document replaces and supercedes WHC-SD-SNF-SD-003.

  2. Cold Vacuum Drying Facility Crane and Hoist System Design Description (SYS 14)

    SciTech Connect (OSTI)

    TRAN, Y.S.

    2000-06-07

    This system design description (SDD) is for the Cold Vacuum Drying (CVD) Facility overhead crane and hoist system. The overhead crane and hoist system is a general service system. It is located in the process bays of the CVD Facility, supports the processes required to drain the water and dry the spent nuclear fuel (SNF) contained in the multi-canister overpacks (MCOs) after they have been removed from the K-Basins. The location of the system in the process bay is shown.

  3. 10 CFR 851 Worker Safety and Health Program (WSHP) Description Document

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Oak Ridge Operations P.O. Box 2001 Oak Ridge, Tennessee 37831- May 2 2, 20 0 7 Dr. Ronald D. Townsend, Director Oak Ridge Institute for Science and Education Mai! Stop 22 Post Office Box I 17 Oak Ridge, Tennessee 37831-0117 Dear Dr. Townsend: CONTRACT NO. DEAC05-06OR23100, OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION (ORISE) 10 CFR 851 WORKER SAFETY AND HEALTH PROGRAM (WSHP) DESCRIPTION DOCUMENT The ORISE WSHP submitted to us on February 26, 2007, was evaluated to provide reasonable assurance

  4. OECD Input-Output Tables | Open Energy Information

    Open Energy Info (EERE)

    714271111,00.html Country: Sweden, Finland, Japan, South Korea, Argentina, Australia, China, Israel, United Kingdom, Portugal, Romania, Greece, Poland, Slovakia, Chile, India,...

  5. OECD-International Platform on Policy Coherence for Development...

    Open Energy Info (EERE)

    Area: Economic Development Topics: Co-benefits assessment Resource Type: Guidemanual, Lessons learnedbest practices, Technical report User Interface: Website Website:...

  6. Quality assurance program description: Hanford Waste Vitrification Plant, Part 1. Revision 3

    SciTech Connect (OSTI)

    Not Available

    1992-12-31

    This document describes the Department of Energy`s Richland Field Office (DOE-RL) quality assurance (QA) program for the processing of high-level waste as well as the Vitrification Project Quality Assurance Program for the design and construction of the Hanford Waste Vitrification Plant (HWVP). It also identifies and describes the planned activities that constitute the required quality assurance program for the HWVP. This program applies to the broad scope of quality-affecting activities associated with the overall HWVP Facility. Quality-affecting activities include designing, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, installing, inspecting, testing, maintaining, repairing, and modifying. Also included are the development, qualification, and production of waste forms which may be safely used to dispose of high-level radioactive waste resulting from national defense activities. The HWVP QA program is made up of many constituent programs that are being implemented by the participating organizations. This Quality Assurance program description is intended to outline and define the scope and application of the major programs that make up the HWVP QA program. It provides a means by which the overall program can be managed and directed to achieve its objectives. Subsequent parts of this description will identify the program`s objectives, its scope, application, and structure.

  7. Time-dependent Hartree-Fock description of heavy-ion collisions. Progress report

    SciTech Connect (OSTI)

    Krieger, S.J.

    1982-01-01

    Given the theoretical difficulties in establishing the validity of the TDHF approximation, it is perhaps most effective at this time to assess the results of the TDHF calculations by comparing them, insofar as is possible, with experimental results. In this task we shall be limited by the fact that the TDHF approximation does not yield an inclusive description of nuclear reactions, but rather an exclusive description of nuclear collisions. Thus the semi-classical nature of the approximation which offers such a simple picture of certain gross properties, at the same time effectively prohibits the acquisition of detailed channel information. In spite of this we shall still succeed in showing rather good agreement between theory and experiment for the particular reactions which result in fusion or in deep inelastic collisions. The structure of this review is as follows. The TDHF equations are derived and briefly discussed. The effective interaction employed in the calculations is described, and some technical aspects of the calculations are discussed. Fusion results are presented along with a brief discussion of deep inelastic collisions. Finally, the results are summarized. (WHK)

  8. Quantum theory as a description of robust experiments: Derivation of the Pauli equation

    SciTech Connect (OSTI)

    De Raedt, Hans; Katsnelson, Mikhail I.; Donker, Hylke C.; Michielsen, Kristel

    2015-08-15

    It is shown that the Pauli equation and the concept of spin naturally emerge from logical inference applied to experiments on a charged particle under the conditions that (i) space is homogeneous (ii) the observed events are logically independent, and (iii) the observed frequency distributions are robust with respect to small changes in the conditions under which the experiment is carried out. The derivation does not take recourse to concepts of quantum theory and is based on the same principles which have already been shown to lead to e.g. the Schrödinger equation and the probability distributions of pairs of particles in the singlet or triplet state. Application to Stern–Gerlach experiments with chargeless, magnetic particles, provides additional support for the thesis that quantum theory follows from logical inference applied to a well-defined class of experiments. - Highlights: • The Pauli equation is obtained through logical inference applied to robust experiments on a charged particle. • The concept of spin appears as an inference resulting from the treatment of two-valued data. • The same reasoning yields the quantum theoretical description of neutral magnetic particles. • Logical inference provides a framework to establish a bridge between objective knowledge gathered through experiments and their description in terms of concepts.

  9. A new Skyrme energy density functional for a better description of spin-isospin resonances

    SciTech Connect (OSTI)

    Roca-Maza, X.; Colò, G.; Cao, Li-Gang; Sagawa, H.

    2015-10-15

    A correct determination of the isospin and spin-isospin properties of the nuclear effective interaction should lead to an accurate description of the Gamow-Teller resonance (GT), the Spin Dipole Resonance (SDR), the Giant Dipole Resonance (GDR) or the Antianalog Giant Dipole Resonance (AGDR), among others. A new Skyrme energy density functional named SAMi is introduced with the aim of going a step forward in setting the bases for a more precise description of spin-isospin resonances [1, 2]. In addition, we will discuss some new features of our analysis on the AGDR in {sup 208}Pb [3] as compared with available experimental data on this resonance [4, 5, 6], and on the GDR [7]. Such study, guided by a simple yet physical pocket formula, has been developed by employing the so called SAMi-J family of systematically varied interactions. This set of interactions is compatible with experimental data for values of the symmetry energy at saturation J and slope parameter L falling in the ranges 31−33 MeV and 75−95 MeV, respectively.

  10. Gambia: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    MWhyear NA 2008 NREL Coal Reserves Unavailable Million Short Tons NA 2008 EIA Natural Gas Reserves Unavailable Cubic Meters (cu m) NA 2010 CIA World Factbook Oil Reserves...