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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. 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:...

  6. 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...

  7. 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...

  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. 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)

  19. 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.

  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. 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...

  7. 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).

  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. 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.

  2. 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)

  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. 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 ...

  9. 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...

  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. 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 ...

  7. 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 ...

  8. 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 ...

  9. 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...

  10. 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 ...

  11. CleanEnergyProjectsonTribalLands_Project_Descriptions_072011...

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

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

  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. 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.

  17. 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.

  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. 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

  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. 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.

  4. 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

  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. 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,

  17. 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

  18. 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 ...

  19. 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...

  20. 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 ...

  1. 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, ...

  2. 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...

  3. 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...

  4. 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 ...

  5. 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 ...

  6. 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...

  7. 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...

  8. 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).

  9. 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 ...

  10. 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 ...

  11. 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...

  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. 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.

  2. 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.

  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. 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.

  8. 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

  9. 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.

  10. 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.

  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. 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

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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

  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. 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

  3. 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.

  4. 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.

  5. 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.

  6. 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

  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. 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 ...

  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 You are accessing a ...

  10. 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 ...

  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. 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.

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. 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.

  9. 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 ...

  10. 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.

  11. 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 ...

  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. 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.

  17. 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.

  18. 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

  19. 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

  20. 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

  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. 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

  5. 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

  6. 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

  7. 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).

  8. 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...

  9. 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...

  10. 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

  11. 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.

  12. 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....

  13. 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...

  14. 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...

  15. 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...

  16. 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 ...

  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. 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.

  1. 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.

  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. 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.

  5. 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.

  6. 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

  7. 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.

  8. 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.

  9. 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.

  10. 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).

  11. 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

  12. 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.

  13. 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

  14. 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

  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. 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.

  17. 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.

  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. 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.

  1. 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.

  2. 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

  3. 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.

  4. 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.

  5. 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.

  6. 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)

  7. 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.

  8. 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,...

  9. 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:...

  10. Montenegro: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    (bbl) 156 2010 CIA World Factbook Energy Maps featuring Montenegro Montenegro global irradiation and solar electricity potential (horizontally-mounted photovoltaic modules)...

  11. 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...

  12. Democratic Republic of Congo: Energy Resources | Open Energy...

    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...

  13. Burkina Faso: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    World Factbook, Appendix D Reegle Clean Energy Datasets Burkina Faso is a country in Africa. External Links Burkina Faso Renewable Energy Data from IEA Burkina Faso Contacts...

  14. 105-K Basin material design basis feed description for spent nuclear fuel project facilities

    SciTech Connect (OSTI)

    Praga, A.N.

    1998-01-08

    Revisions 0 and 0A of this document provided estimated chemical and radionuclide inventories of spent nuclear fuel and sludge currently stored within the Hanford Site`s 105-K Basins. This Revision (Rev. 1) incorporates the following changes into Revision 0A: (1) updates the tables to reflect: improved cross section data, a decision to use accountability data as the basis for total Pu, a corrected methodology for selection of the heat generation basis fee, and a revised decay date; (2) adds section 3.3.3.1 to expand the description of the approach used to calculate the inventory values and explain why that approach yields conservative results; (3) changes the pre-irradiation braze beryllium value.

  15. Structure Discovery in Large Semantic Graphs Using Extant Ontological Scaling and Descriptive Statistics

    SciTech Connect (OSTI)

    al-Saffar, Sinan; Joslyn, Cliff A.; Chappell, Alan R.

    2011-07-18

    As semantic datasets grow to be very large and divergent, there is a need to identify and exploit their inherent semantic structure for discovery and optimization. Towards that end, we present here a novel methodology to identify the semantic structures inherent in an arbitrary semantic graph dataset. We first present the concept of an extant ontology as a statistical description of the semantic relations present amongst the typed entities modeled in the graph. This serves as a model of the underlying semantic structure to aid in discovery and visualization. We then describe a method of ontological scaling in which the ontology is employed as a hierarchical scaling filter to infer different resolution levels at which the graph structures are to be viewed or analyzed. We illustrate these methods on three large and publicly available semantic datasets containing more than one billion edges each. Keywords-Semantic Web; Visualization; Ontology; Multi-resolution Data Mining;

  16. Thermodynamic and structural description of europium complexation in 1-octanol solution

    SciTech Connect (OSTI)

    Charbonnel, M.C.; Vu, T.H.; Boubals, N.; Couston, L.

    2008-07-01

    Polydentate N-bearing ligands such as bis-triazinyl-pyridines (BTPS) are interesting extractants for actinide(III)/lanthanide(III) separation. A description of europium complexation in 1-octanol solutions was undertaken to enhance the knowledge of the extraction mechanisms. Time- Resolved Laser-Induced Fluorescence (TRLIF) spectroscopy allows determination of the first solvation shell for europium(III) nitrate, chloride, and perchlorate with different amounts of water. Europium nitrate complexation by iPr-BTP was then studied by TRLIF and microcalorimetry; the stability constant related to the formation of Eu(BTP){sub 3}{sup 3+} is similar by both techniques (log {beta}{sub 3} = 11.3 {+-} 0.5). The difference of solvation of the cation seems to have an influence on the thermodynamic properties related to the complexation with organic ligands. (authors)

  17. Radioactive Solid Waste Storage and Disposal at Oak Ridge National Laboratory, Description and Safety Analysis

    SciTech Connect (OSTI)

    Bates, L.D.

    2001-01-30

    Oak Ridge National Laboratory (ORNL) is a principle Department of Energy (DOE) Research Institution operated by the Union Carbide Corporation - Nuclear Division (UCC-ND) under direction of the DOE Oak Ridge Operations Office (DOE-ORO). The Laboratory was established in east Tennessee, near what is now the city of Oak Ridge, in the mid 1940s as a part of the World War II effort to develop a nuclear weapon. Since its inception, disposal of radioactively contaminated materials, both solid and liquid, has been an integral part of Laboratory operations. The purpose of this document is to provide a detailed description of the ORNL Solid Waste Storage Areas, to describe the practice and procedure of their operation, and to address the health and safety impacts and concerns of that operation.

  18. Description of microstructural intragranular heterogeneities in a Ti-IF steel using a micromechanical approach

    SciTech Connect (OSTI)

    Wauthier, A.; Brenner, R.; Bacroix, B.; Regle, H.

    2007-04-07

    A classical problem in metallurgical research is to control the recrystallisation texture which forms during the last annealing process and which determine the mechanical behaviour of the final products. It is now widely admitted that the local deformed state and the substructural heterogeneities within the polycrystal are key parameters to understand the recrystallisation mechanisms.In this work, we present a micromechanical approach based on the use of the affine extension of the self-consistent scheme for viscoplastic behaviours and a phenomenological description of dislocation patterning using a hardening model recently developed for two-stage strain paths. These two ingredients allow to compare the model with experimental crystallographic texture after rolling as well as experimental observations of the intragranular substructure using orientation imaging by Electron Back-Scattered Diffaction. It is shown that the rolling texture is correctly simulated and successful predictions of the orientation of dislocation sheets are obtained.

  19. In Situ Permeable Flow Sensor installation at 100-H description of work

    SciTech Connect (OSTI)

    Vaught, D.J.

    1994-04-18

    This description of work details field activities associated with drilling four boreholes in the 100-HR-3 Operable Unit for placement of four In Situ Permeable Flow Sensors near the 183-H Basin. A sonic drill rig funded under a Cooperative Research and Development Agreement (CRADA) will be employed to drill the boreholes. This project includes installation of automatic data logging and telemetry equipment. Each Sensor will be supplied with a data logger at the surface which will be wired to a cellular phone on site or to an existing telemetry station to transmit data to a computer in 2440 Stevens Center. Power to operate the Sensors and data loggers will be supplied by a small gasoline or diesel generator. Processed data will be used to develop a three-dimensional flownet of the unconfined aquifer near and within the Columbia River influenced mixing zone.

  20. Cold Vacuum Dryer (CVD) Facility Fire Protection System Design Description (SYS 24)

    SciTech Connect (OSTI)

    SINGH, G.

    2000-10-17

    This system design description (SDD) addresses the Cold Vacuum Drying (CVD) Facility fire protection system (FPS). The primary features of the FPS for the CVD are a fire alarm and detection system, automatic sprinklers, and fire hydrants. The FPS also includes fire extinguishers located throughout the facility and fire hydrants to assist in manual firefighting efforts. In addition, a fire barrier separates the operations support (administrative) area from the process bays and process bay support areas. Administrative controls to limit combustible materials have been established and are a part of the overall fire protection program. The FPS is augmented by assistance from the Hanford Fire Department (HED) and by interface systems including service water, electrical power, drains, instrumentation and controls. This SDD, when used in conjunction with the other elements of the definitive design package, provides a complete picture of the FPS for the CVD Facility.

  1. Application of fractal theory in refined reservoir description for EOR pilot area

    SciTech Connect (OSTI)

    Yue Li; Yonggang Duan; Yun Li; Yuan Lu

    1997-08-01

    A reliable reservoir description is essential to investigate scenarios for successful EOR pilot test. Reservoir characterization includes formation composition, permeability, porosity, reservoir fluids and other petrophysical parameters. In this study, various new tools have been applied to characterize Kilamayi conglomerate formation. This paper examines the merits of various statistical methods for recognizing rock property correlation in vertical columns and gives out methods to determine fractal dimension including R/S analysis and power spectral analysis. The paper also demonstrates that there is obvious fractal characteristics in conglomerate reservoirs of Kilamayi oil fields. Well log data in EOR pilot area are used to get distribution profile of parameters including permeability, porosity, water saturation and shale content.

  2. A statistical description of the types and severities of accidents involving tractor semi-trailers

    SciTech Connect (OSTI)

    Clauss, D.B.; Wilson, R.K.; Blower, D.F.; Campbell, K.L.

    1994-06-01

    This report provides a statistical description of the types and severities of tractor semi-trailer accidents involving at least one fatality. The data were developed for use in risk assessments of hazardous materials transportation. Several accident databases were reviewed to determine their suitability to the task. The TIFA (Trucks Involved in Fatal Accidents) database created at the University of Michigan Transportation Research Institute was extensively utilized. Supplementary data on collision and fire severity, which was not available in the TIFA database, were obtained by reviewing police reports for selected TIFA accidents. The results are described in terms of frequencies of different accident types and cumulative distribution functions for the peak contact velocity, rollover skid distance, fire temperature, fire size, fire separation, and fire duration.

  3. Description of work for 100-N Hanford Generating Plant settling pond drilling and sampling

    SciTech Connect (OSTI)

    Galbraith, R.P.

    1993-09-01

    This description of work details the field activities associated with borehole drilling and sampling of the 100-N Hanford Generating Plant (HGP) Settling Pond and will serve as a field guide for those performing the work. It should be used in conjunction with the Environmental Investigations and Site Characterization Manual (WHC 1988a) for specific procedures. The borehole location is shown in Figure 1. The settling pond, the dimensions of which are 40 m by 16 m (131.3 ft by 52.5 ft), is located at the HGP adjacent to the 100-N Area. The pond received process water from the plant. The water contained trace oxygen scavenging conditioners such as morpholine, hydrazine, and ammonia. Surface radioactivity readings are 150 to 500 cpm. Trace levels of surface contamination are present. Drilling and sampling will be in accordance with procedures in the EII manual (WHC 1988a).

  4. Innovative techniques for the description of reservoir heterogeneity using tracers. Final report, October 1992--December 1993

    SciTech Connect (OSTI)

    Pope, G.A.; Sepehrnoori, K.; Delshad, M.; Ferreira, L.; Gupta, A.; Maroongroge, V.

    1994-11-01

    This is the final report of a three year research project on the use of tracers for reservoir characterization. The objective of this research was to develop advanced, innovative techniques for the description of reservoir characteristics using both single-well backflow and interwell tracer tests. (1) The authors implemented and validated tracer modeling features in a compositional simulator (UTCOMP). (2) They developed and applied a new single well tracer test for estimating reservoir heterogeneity. (3) They developed and applied a new single well tracer test for estimating reservoir wettability in-situ. (4) They developed a new, simple and efficient method to analyze two well tracer tests based upon type curve matching and illustrated its use with actual field tracer data. (5) They developed a new method for deriving an integrated reservoir description based upon combinatorial optimization schemes. (6) They developed a new, interwell tracer test for reservoir heterogeneity called vertical tracer profiling (VTP) and demonstrated its advantages over conventional interwell tracer testing. (7) They developed a simple and easy analytical method to estimate swept pore volume from interwell tracer data and showed both the theoretical basis for this method and its practical utility. (8) They made numerous enhancements to our compositional reservoir simulator such as including the full permeability tensor, adding faster solvers, improving its speed and robustness and making it easier to use (better I/0) for tracer simulation problems. (9) They applied the enhanced version of UTCOMP to the analysis of interwell tracer data using perfluorocarbons at Elks Hill Naval Petroleum Reserve. All of these accomplishments taken together have significantly improved the state of reservoir tracer technology and have demonstrated that it is a far more powerful and useful tool for quantitative reservoir characterization than previously realized or practiced by the industry.

  5. Hydrodynamic description of an unmagnetized plasma with multiple ion species. I. General formulation

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

    Simakov, Andrei Nikolaevich; Molvig, Kim

    2016-03-17

    A generalization of the Braginskii ion fluid description [S. I. Braginskii, Sov. Phys. JETP 6, 358 (1958)] to the case of an unmagnetized collisional plasma with multiple ion species is presented. An asymptotic expansion in the ion Knudsen number is used to derive the individual ion species continuity, as well as the total ion mass density, momentum, and energy evolution equations accurate through the second order. Expressions for the individual ion species drift velocities with respect to the center of mass reference frame, as well as for the total ion heat flux and viscosity, which are required to close themore » fluid equations, are evaluated in terms of the first-order corrections to the lowest order Maxwellian ion velocity distribution functions. A variational formulation for evaluating such corrections and its relation to the plasma entropy are presented. Employing trial functions for the corrections, written in terms of expansions in generalized Laguerre polynomials, and maximizing the resulting functionals produces two systems of linear equations (for “vector” and “tensor” portions of the corrections) for the expansion coefficients. A general matrix formulation of the linear systems as well as expressions for the resulting transport fluxes are presented in forms convenient for numerical implementation. The general formulation is employed in the companion paper [A. N. Simakov and K. Molvig, Hydrodynamic description of an unmagnetized plasma with multiple ion species. II. Two and three ion species plasmas, submitted to Phys. Plasmas (2015)] to evaluate the individual ion drift velocities and the total ion heat flux and viscosity for specific cases of two and three ion species plasmas.« less

  6. Description and performance of track and primary-vertex reconstruction with the CMS tracker

    SciTech Connect (OSTI)

    Chatrchyan, Serguei

    2014-10-16

    A description is provided of the software algorithms developed for the CMS tracker both for reconstructing charged-particle trajectories in proton-proton interactions and for using the resulting tracks to estimate the positions of the LHC luminous region and individual primary-interaction vertices. Despite the very hostile environment at the LHC, the performance obtained with these algorithms is found to be excellent. For tbar t events under typical 2011 pileup conditions, the average track-reconstruction efficiency for promptly-produced charged particles with transverse momenta of pT > 0.9GeV is 94% for pseudorapidities of |?| < 0.9 and 85% for 0.9 < |?| < 2.5. The inefficiency is caused mainly by hadrons that undergo nuclear interactions in the tracker material. For isolated muons, the corresponding efficiencies are essentially 100%. For isolated muons of pT = 100GeV emitted at |?| < 1.4, the resolutions are approximately 2.8% in pT, and respectively, 10?m and 30?m in the transverse and longitudinal impact parameters. The position resolution achieved for reconstructed primary vertices that correspond to interesting pp collisions is 1012?m in each of the three spatial dimensions. The tracking and vertexing software is fast and flexible, and easily adaptable to other functions, such as fast tracking for the trigger, or dedicated tracking for electrons that takes into account bremsstrahlung.

  7. Process Options Description for Vitrification Flowsheet Model of INEEL Sodium Bearing Waste

    SciTech Connect (OSTI)

    Nichols, T.T.; Taylor, D.D.; Lauerhass, L.; Barnes, C.M.

    2002-02-21

    The technical information required for the development of a basic steady-state process simulation of the vitrification treatment train of sodium bearing waste (SBW) at Idaho National Engineering and Environmental Laboratory (INEEL) is presented. The objective of the modeling effort is to provide the predictive capability required to optimize an entire treatment train and assess system-wide impacts of local changes at individual unit operations, with the aim of reducing the schedule and cost of future process/facility design efforts. All the information required a priori for engineers to construct and link unit operation modules in a commercial software simulator to represent the alternative treatment trains is presented. The information is of a mid- to high-level nature and consists of the following: (1) a description of twenty-four specific unit operations--their operating conditions and constraints, primary species and key outputs, and the initial modeling approaches that will be used in the first year of the simulation's development; (2) three potential configurations of the unit operations (trains) and their interdependencies via stream connections; and (3) representative stream compositional makeups.

  8. Description of thermal entanglement with the static path plus random-phase approximation

    SciTech Connect (OSTI)

    Canosa, N.; Matera, J. M.; Rossignoli, R.

    2007-08-15

    We discuss the application of the static path plus random-phase approximation (SPA+RPA) and the ensuing mean field+RPA treatment to the evaluation of entanglement in composite quantum systems at finite temperature. These methods involve just local diagonalizations and the determination of the generalized collective vibrational frequencies. As an illustration, we evaluate the pairwise entanglement in a fully connected XXZ chain of n spins at finite temperature in a transverse magnetic field b. It is shown that already the mean field+RPA provides an accurate analytic description of the concurrence below the mean field critical region (vertical bar b vertical bar 0 weak entanglement also arises when the ground state is separable (vertical bar b vertical bar >b{sub c}), with the limit temperature for pairwise entanglement exhibiting quite distinct regimes for vertical bar b vertical bar b{sub c}.

  9. Description and performance of track and primary-vertex reconstruction with the CMS tracker

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

    Chatrchyan, Serguei

    2014-10-16

    A description is provided of the software algorithms developed for the CMS tracker both for reconstructing charged-particle trajectories in proton-proton interactions and for using the resulting tracks to estimate the positions of the LHC luminous region and individual primary-interaction vertices. Despite the very hostile environment at the LHC, the performance obtained with these algorithms is found to be excellent. For tbar t events under typical 2011 pileup conditions, the average track-reconstruction efficiency for promptly-produced charged particles with transverse momenta of pT > 0.9GeV is 94% for pseudorapidities of |η| < 0.9 and 85% for 0.9 < |η| < 2.5. Themore » inefficiency is caused mainly by hadrons that undergo nuclear interactions in the tracker material. For isolated muons, the corresponding efficiencies are essentially 100%. For isolated muons of pT = 100GeV emitted at |η| < 1.4, the resolutions are approximately 2.8% in pT, and respectively, 10μm and 30μm in the transverse and longitudinal impact parameters. The position resolution achieved for reconstructed primary vertices that correspond to interesting pp collisions is 10–12μm in each of the three spatial dimensions. The tracking and vertexing software is fast and flexible, and easily adaptable to other functions, such as fast tracking for the trigger, or dedicated tracking for electrons that takes into account bremsstrahlung.« less

  10. Process Options Description for Steam Reforming Flowsheet Model of INEEL Tank Farm Waste

    SciTech Connect (OSTI)

    Taylor, D.D.; Barnes, C.M.; Nichols, T.T.

    2002-05-21

    Technical information is provided herein that is required for development of a steady-state process simulation of a baseline steam reforming treatment train for Tank Farm waste at the Idaho National Engineering and Environmental Laboratory (INEEL). This document supercedes INEEL/EXT-2001-173, produced in FY2001 to support simulation of the direct vitrification treatment train which was the previous process baseline. A process block flow diagram for steam reforming is provided, together with a list of unit operations which constitute the process. A detailed description of each unit operation is given which includes its purpose, principal phenomena present, expected pressure and temperature ranges, key chemical species in the inlet steam, and the proposed manner in which the unit operation is to be modeled in the steady state process simulation. Models for the unit operations may be mechanistic (based on first principles), empirical (based solely on pilot test data without extrapolation) , or by correlations (based on extrapolative or statistical schemes applied to pilot test data). Composition data for the expected process feed streams is provided.

  11. Nevada National Security Site Environmental Report 2012 Attachment A: Site Description

    SciTech Connect (OSTI)

    Wills, Cathy A

    2013-09-11

    This attachment expands on the general description of the Nevada National Security Site (NNSS) presented in the Introduction to the Nevada National Security Site Environmental Report 2012 (National Security Technologies, LLC [NSTec], 2013). Included are subsections that summarize the site’s geological, hydrological, climatological, and ecological setting and the cultural resources of the NNSS. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NNSS. 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 NNSS. The NNSS 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 NNSS operations. These key features include the general remote location of the NNSS, 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.

  12. Nevada National Security Site Environmental Report 2011 Attachment A: Site Description

    SciTech Connect (OSTI)

    Cathy Wills, ed.

    2012-09-12

    This attachment expands on the general description of the Nevada National Security Site (NNSS) presented in the Introduction to the Nevada National Security Site Environmental Report 2011. Included are subsections that summarize the site's geological, hydrological, climatological, and ecological setting and the cultural resources of the NNSS. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NNSS. 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 NNSS. The NNSS 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 NNSS operations. These key features include the general remote location of the NNSS, 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.

  13. Nevada National Security Site Environmental Report 2013 Attachment A: Site Description

    SciTech Connect (OSTI)

    Wills, C.

    2014-09-09

    This attachment expands on the general description of the Nevada National Security Site (NNSS) presented in the Introduction to the Nevada National Security Site Environmental Report 2012 (National Security Technologies, LLC [NSTec], 2013). Included are subsections that summarize the site’s geological, hydrological, climatological, and ecological setting and the cultural resources of the NNSS. The subsections are meant to aid the reader in understanding the complex physical and biological environment of the NNSS. 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 NNSS. The NNSS 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 NNSS operations. These key features include the general remote location of the NNSS, 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.

  14. Microscopic description of anisotropic low-density dipolar Bose gases in two dimensions

    SciTech Connect (OSTI)

    Macia, A.; Mazzanti, F.; Boronat, J.; Zillich, R. E.

    2011-09-15

    A microscopic description of the zero-energy two-body ground state and many-body static properties of anisotropic homogeneous gases of bosonic dipoles in two dimensions at low densities is presented and discussed. By changing the polarization angle with respect to the plane, we study the impact of the anisotropy, present in the dipole-dipole interaction, on the energy per particle, comparing the results with mean-field predictions. We restrict the analysis to the regime where the interaction is always repulsive, although the strength of the repulsion depends on the orientation with respect to the polarization field. We present a series expansion of the solution of the zero-energy two-body problem, which allows us to find the scattering length of the interaction and to build a suitable Jastrow factor that we use as a trial wave function for both a variational and diffusion Monte Carlo simulation of the infinite system. We find that the anisotropy has an almost negligible impact on the ground-state properties of the many-body system in the universal regime where the scattering length governs the physics of the system. We also show that scaling in the gas parameter persists in the dipolar case up to values where other isotropic interactions with the same scattering length yield different predictions.

  15. General description of electromagnetic radiation processes based on instantaneous charge acceleration in ''endpoints''

    SciTech Connect (OSTI)

    James, Clancy W.; Falcke, Heino; Huege, Tim; Ludwig, Marianne

    2011-11-15

    We present a methodology for calculating the electromagnetic radiation from accelerated charged particles. Our formulation - the 'endpoint formulation' - combines numerous results developed in the literature in relation to radiation arising from particle acceleration using a complete, and completely general, treatment. We do this by describing particle motion via a series of discrete, instantaneous acceleration events, or 'endpoints', with each such event being treated as a source of emission. This method implicitly allows for particle creation and destruction, and is suited to direct numerical implementation in either the time or frequency domains. In this paper we demonstrate the complete generality of our method for calculating the radiated field from charged particle acceleration, and show how it reduces to the classical named radiation processes such as synchrotron, Tamm's description of Vavilov-Cherenkov, and transition radiation under appropriate limits. Using this formulation, we are immediately able to answer outstanding questions regarding the phenomenology of radio emission from ultra-high-energy particle interactions in both the earth's atmosphere and the moon. In particular, our formulation makes it apparent that the dominant emission component of the Askaryan effect (coherent radio-wave radiation from high-energy particle cascades in dense media) comes from coherent 'bremsstrahlung' from particle acceleration, rather than coherent Vavilov-Cherenkov radiation.

  16. Towards a nonequilibrium Green's function description of nuclear reactions: One-dimensional mean-field dynamics

    SciTech Connect (OSTI)

    Rios, Arnau; Barker, Brent; Buchler, Mark; Danielewicz, Pawel

    2011-05-15

    Research Highlights: > Dynamics of central nuclear reactions. > Nonequilibrium Green's functions and Kadanoff-Baym formalism. > Adiabatic switching on of interactions. > Mean-field time evolution of nuclear slabs. > Off-diagonal spatial structure of a collision density matrix. - Abstract: Nonequilibrium Green's function methods allow for an intrinsically consistent description of the evolution of quantal many-body body systems, with inclusion of different types of correlations. In this paper, we focus on the practical developments needed to build a Green's function methodology for nuclear reactions. We start out by considering symmetric collisions of slabs in one dimension within the mean-field approximation. We concentrate on two issues of importance for actual reaction simulations. First, the preparation of the initial state within the same methodology as for the reaction dynamics is demonstrated by an adiabatic switching on of the mean-field interaction, which leads to the mean-field ground state. Second, the importance of the Green's function matrix-elements far away from the spatial diagonal is analyzed by a suitable suppression process that does not significantly affect the evolution of the elements close to the diagonal. The relative lack of importance of the far-away elements is tied to system expansion. We also examine the evolution of the Wigner function and verify quantitatively that erasing of the off-diagonal elements corresponds to averaging out of the momentum-space details in the Wigner function.

  17. Description of work for 216-U-Pond cone penetrometer demonstration

    SciTech Connect (OSTI)

    Kelty, G.G.

    1993-08-01

    This description of work details the Proposed field activities associated with Cone Penetrometer (CPT) work at the 216-U-10 Pond (U-10 Pond) in the 200 West Area and will serve as a field guide for those performing the work. The U-10 Pond was constructed in 1944 to receive low-level liquid effluent from the various chemical reprocessing facilities within the 200 West Area. The U-10 Pond covered 30 acres and received approximately 4.3 {times} 10{sup 10} gal of contaminated liquid. Sampling conducted in 1980 indicated that the most significant radionuclides were {sup 90}Sr, {sup 137}Cs, plutonium, and uranium (DOE-RL 1993). The pond was deactivated and stabilized in 1985 with clean fill dirt. The thickness of the stabilization cover is variable across the former pond and ranges between 2 ft near the pond margins and delta area to 8 feet in the deepest section of the pond. The purpose of this work is to establish the extent of contamination beneath the U-10 pond.

  18. Hybrid density functional theory description of N- and C-doping of NiO

    SciTech Connect (OSTI)

    Nolan, Michael; Long, Run; English, Niall J.; Mooney, Damian A.

    2011-06-14

    The large intrinsic bandgap of NiO hinders its potential application as a photocatalyst under visible-light irradiation. In this study, we have performed first-principles screened exchange hybrid density functional theory with the HSE06 functional calculations of N- and C-doped NiO to investigate the effect of doping on the electronic structure of NiO. C-doping at an oxygen site induces gap states due to the dopant, the positions of which suggest that the top of the valence band is made up primarily of C 2p-derived states with some Ni 3d contributions, and the lowest-energy empty state is in the middle of the gap. This leads to an effective bandgap of 1.7 eV, which is of potential interest for photocatalytic applications. N-doping induces comparatively little dopant-Ni 3d interactions, but results in similar positions of dopant-induced states, i.e., the top of the valence band is made up of dopant 2p states and the lowest unoccupied state is the empty gap state derived from the dopant, leading to bandgap narrowing. With the hybrid density functional theory (DFT) results available, we discuss issues with the DFT corrected for on-site Coulomb description of these systems.

  19. Property description and fact-finding report for NOSR 1&3, Garfield County, Colorado

    SciTech Connect (OSTI)

    1996-06-30

    The US Department of Energy has asked Gustavson Associates, Inc. to serve as an Independent Petroleum Consultant under contract DE-AC01-96FE64202. This authorizes a study and recommendations regarding future development of Naval Oil Shale No. 1 and No. 3 (NOSR 1 and 3) in Garfield County, Colorado. The report that follows is the Phase I fact-finding and property description for that study. The United States of America claims ownership of 100 percent of the minerals and 100 percent of the surface rights in 36,406-acre NOSR-1 and 20,171-acre at NOSR-3. Production has been established on NOSR-3 and currently the DOE owns interests in 53 gas wells that produce on or immediately adjacent to the acreage. NOSR-3 also contains undrilled locations that are classified as proved undeveloped or probable reserves. Recently, the Colorado Oil and Gas Commission (COGCC) approved an increased 40 acre drilling density for the Mesaverde formation that includes portions of NOSR-3.

  20. Experimental determination of lead carbonate solubility at high ionic strengths: A Pitzer model description

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

    Xiong, Yongliang

    2015-05-06

    In this article, solubility measurements of lead carbonate, PbCO3(cr), cerussite, as a function of total ionic strengths are conducted in the mixtures of NaCl and NaHCO3 up to I = 1.2 mol•kg–1 and in the mixtures of NaHCO3 and Na2CO3 up to I = 5.2 mol•kg–1, at room temperature (22.5 ± 0.5 °C). The solubility constant (log Ksp) for cerussite, PbCO3(cr) = Pb2+ + CO32- was determined as –13.76 ± 0.15 (2σ) with a set of Pitzer parameters describing the specific interactions of PbCO3(aq), Pb(CO3)22-, and Pb(CO3)Cl– with the bulk-supporting electrolytes, based on the Pitzer model. The model developed inmore » this work can reproduce the experimental results including model-independent solubility values from the literature over a wide range of ionic strengths with satisfactory accuracy. The model is expected to find applications in numerous fields, including the accurate description of chemical behavior of lead in geological repositories, the modeling of formation of oxidized Pb–Zn ore deposits, and the environmental remediation of lead contamination.« less

  1. Description of work for 200-UP-1 characterization of monitoring wells

    SciTech Connect (OSTI)

    Innis, B.E.; Kelty, G.G.

    1994-02-01

    This description of work (DOW) details the field activities associated with the drilling, soil sampling, and construction of groundwater monitoring and dual-use wells in the 200-UP-1 Operable Unit (Tasks 2, 3, and 5 in the 200-UP-1 RI/FS Work Plan DOE/RL 1993a) and will serve as a field guide for those performing the work. It will be used in conjunction with the Remedial Investigation/Feasibility Study Work Plan for the 200-UP-1 Groundwater operable Unit (DOE-RL 1993a, [LFI]) and Site Characterization Manual (WHC 1988a). Groundwater wells are being constructed to characterize the vertical and horizontal extent of the Uranium and {sup 99}{Tc} plumes and to define aquifer properties such as hydraulic communication between aquifers and hydrostratigraphy. Some of these wells may be utilized for extraction purposes during the IRM phase anticipated at this operable unit and are being designed with a dual use in mind. These data will be used to optimize the Interim Remedial Measures (IRM) for the cleanup of these two plumes. The data will also be used with later Limited Field Investigation (LFI) data to perform a Qualitative Risk Assessment (QRA) for the operable unit. The locations for the proposed groundwater wells are presented in Figure 1. The contaminants of concern for the project are presented ih Table 1.

  2. Description of Regional Superfund pilots. Excerpts from `Status of Regional Superfund pilots: End-of-year report`

    SciTech Connect (OSTI)

    1994-12-31

    Following are brief descriptions of the Regional Superfund pilots excerpted from OSWER Publication 9202.1-15A entitled, ``Status of Regional Superfund Pilots: End of Year Report`` (NTIS {number_sign}PB94-963216). The above-referenced report provides greater detail on each pilot`s goals, status and results to date.

  3. Description of the yrast states in {sup 24}Mg by the self-consistent 3D-cranking model

    SciTech Connect (OSTI)

    Oi, Makito

    2005-11-01

    With the self-consistent 3D-cranking model, the ground-state rotational band in {sup 24}Mg is analyzed. The role of triaxial deformation is discussed, in particular in a description of the observed two I{sup {pi}}=8{sup +} states.

  4. Groundwater heat pumps: an examination of hydrogeologic, environmental, legal, and economic factors affecting their use. Volume II. Appendix D, state hydrogeologic descriptions and maps

    SciTech Connect (OSTI)

    Armitage, Dana M.; Bacon, Douglas J.; Massey-Norton, John T.; Miller, James M.

    1980-11-01

    This appendix to the groundwater heat pump report contains hydrogeologic descriptions of the 48 conterminous US with data on ground water quality.

  5. A physical description of fission product behavior fuels for advanced power reactors.

    SciTech Connect (OSTI)

    Kaganas, G.; Rest, J.; Nuclear Engineering Division; Florida International Univ.

    2007-10-18

    The Global Nuclear Energy Partnership (GNEP) is considering a list of reactors and nuclear fuels as part of its chartered initiative. Because many of the candidate materials have not been explored experimentally under the conditions of interest, and in order to economize on program costs, analytical support in the form of combined first principle and mechanistic modeling is highly desirable. The present work is a compilation of mechanistic models developed in order to describe the fission product behavior of irradiated nuclear fuel. The mechanistic nature of the model development allows for the possibility of describing a range of nuclear fuels under varying operating conditions. Key sources include the FASTGRASS code with an application to UO{sub 2} power reactor fuel and the Dispersion Analysis Research Tool (DART ) with an application to uranium-silicide and uranium-molybdenum research reactor fuel. Described behavior mechanisms are divided into subdivisions treating fundamental materials processes under normal operation as well as the effect of transient heating conditions on these processes. Model topics discussed include intra- and intergranular gas-atom and bubble diffusion, bubble nucleation and growth, gas-atom re-solution, fuel swelling and ?scion gas release. In addition, the effect of an evolving microstructure on these processes (e.g., irradiation-induced recrystallization) is considered. The uranium-alloy fuel, U-xPu-Zr, is investigated and behavior mechanisms are proposed for swelling in the {alpha}-, intermediate- and {gamma}-uranium zones of this fuel. The work reviews the FASTGRASS kinetic/mechanistic description of volatile ?scion products and, separately, the basis for the DART calculation of bubble behavior in amorphous fuels. Development areas and applications for physical nuclear fuel models are identified.

  6. Experimental determination of lead carbonate solubility at high ionic strengths: A Pitzer model description

    SciTech Connect (OSTI)

    Xiong, Yongliang

    2015-05-06

    In this article, solubility measurements of lead carbonate, PbCO3(cr), cerussite, as a function of total ionic strengths are conducted in the mixtures of NaCl and NaHCO3 up to I = 1.2 mol•kg–1 and in the mixtures of NaHCO3 and Na2CO3 up to I = 5.2 mol•kg–1, at room temperature (22.5 ± 0.5 °C). The solubility constant (log Ksp) for cerussite, PbCO3(cr) = Pb2+ + CO32- was determined as –13.76 ± 0.15 (2σ) with a set of Pitzer parameters describing the specific interactions of PbCO3(aq), Pb(CO3)22-, and Pb(CO3)Cl with the bulk-supporting electrolytes, based on the Pitzer model. The model developed in this work can reproduce the experimental results including model-independent solubility values from the literature over a wide range of ionic strengths with satisfactory accuracy. The model is expected to find applications in numerous fields, including the accurate description of chemical behavior of lead in geological repositories, the modeling of formation of oxidized Pb–Zn ore deposits, and the environmental remediation of lead contamination.

  7. Fixed-bed gasification research using US coals. Volume 1. Program and facility description

    SciTech Connect (OSTI)

    Thimsen, D.; Maurer, R.E.; Poole, A.R.; Pui, D.; Liu, B.; Kittleson, D.

    1984-10-01

    The United States Department of Interior, Bureau of Mines, Twin Cities Research Center, Minneapolis, Minnesota is the site of a 6.5 foot diameter Wellman-Galusha gasifier, installed in 1977-1978. This gasifier, combustor/incinerator, and flue gas scrubber system in the past had been operated jointly by Bureau of Mines personnel, personnel from member companies of the Mining and Industrial Fuel Gas Group, and United States Department of Energy personnel-consultants. Numerous tests using a variety of coals have to date been performed. In May of 1982, Black, Sivalls and Bryson, Incorporated (BS and B) was awarded the contract to plan, execute, and report gasification test performance data from this small industrial fixed-bed gasification test facility. BS and B is responsible for program administration, test planning, test execution, and all documentation of program activities and test reports. The University of Minnesota, Particle Technology Laboratory (UMPTL) is subcontractor to BS and B to monitor process parameters, and provide analysis for material inputs and outputs. This report is the initial volume in a series of reports describing the fixed-bed gasification of US coals at the Bureau of Mines, Twin Cities Research Center. A history of the program is given in Section 1 and a thorough description of the facility in Section 2. The operation of the facility is described in Section 3. Monitoring systems and procedures are described in Sections 4 and 5. Data reduction tools are outlined in Section 6. There is no executive summary or conclusions as this volume serves only to describe the research program. Subsequent volumes will detail each gasification test and other pertinent results of the gasification program. 32 references, 23 figures, 15 tables.

  8. CONCEPTUAL PROCESS DESCRIPTION FOR THE MANUFACTURE OF LOW-ENRICHED URANIUM-MOLYBDENUM FUEL

    SciTech Connect (OSTI)

    Daniel M. Wachs; Curtis R. Clark; Randall J. Dunavant

    2008-02-01

    The National Nuclear Security Agency Global Threat Reduction Initiative (GTRI) is tasked with minimizing the use of high-enriched uranium (HEU) worldwide. A key component of that effort is the conversion of research reactors from HEU to low-enriched uranium (LEU) fuels. The GTRI Convert Fuel Development program, previously known as the Reduced Enrichment for Research and Test Reactors program was initiated in 1978 by the United States Department of Energy to develop the nuclear fuels necessary to enable these conversions. The program cooperates with the research reactors’ operators to achieve this goal of HEU to LEU conversion without reduction in reactor performance. The programmatic mandate is to complete the conversion of all civilian domestic research reactors by 2014. These reactors include the five domestic high-performance research reactors (HPRR), namely: the High Flux Isotope Reactor at the Oak Ridge National Laboratory, the Advanced Test Reactor at the Idaho National Laboratory, the National Bureau of Standards Reactor at the National Institute of Standards and Technology, the Missouri University Research Reactor at the University of Missouri–Columbia, and the MIT Reactor-II at the Massachusetts Institute of Technology. Characteristics for each of the HPRRs are given in Appendix A. The GTRI Convert Fuel Development program is currently engaged in the development of a novel nuclear fuel that will enable these conversions. The fuel design is based on a monolithic fuel meat (made from a uranium-molybdenum alloy) clad in Al-6061 that has shown excellent performance in irradiation testing. The unique aspects of the fuel design, however, necessitate the development and implementation of new fabrication techniques and, thus, establishment of the infrastructure to ensure adequate fuel fabrication capability. A conceptual fabrication process description and rough estimates of the total facility throughput are described in this document as a basis for

  9. THE HST/ACS COMA CLUSTER SURVEY. II. DATA DESCRIPTION AND SOURCE CATALOGS

    SciTech Connect (OSTI)

    Hammer, Derek; Verdoes Kleijn, Gijs; Den Brok, Mark; Peletier, Reynier F.; Hoyos, Carlos; Balcells, Marc; Aguerri, Alfonso L.; Ferguson, Henry C.; Goudfrooij, Paul; Carter, David; Guzman, Rafael; Smith, Russell J.; Lucey, John R.; Graham, Alister W.; Trentham, Neil; Peng, Eric; Puzia, Thomas H.; Jogee, Shardha; Batcheldor, Dan; Bridges, Terry J.

    2010-11-15

    The Coma cluster, Abell 1656, was the target of an HST-ACS Treasury program designed for deep imaging in the F475W and F814W passbands. Although our survey was interrupted by the ACS instrument failure in early 2007, the partially completed survey still covers {approx}50% of the core high-density region in Coma. Observations were performed for 25 fields that extend over a wide range of cluster-centric radii ({approx}1.75 Mpc or 1{sup 0}) with a total coverage area of 274 arcmin{sup 2}. The majority of the fields are located near the core region of Coma (19/25 pointings) with six additional fields in the southwest region of the cluster. In this paper, we present reprocessed images and SEXTRACTOR source catalogs for our survey fields, including a detailed description of the methodology used for object detection and photometry, the subtraction of bright galaxies to measure faint underlying objects, and the use of simulations to assess the photometric accuracy and completeness of our catalogs. We also use simulations to perform aperture corrections for the SEXTRACTOR Kron magnitudes based only on the measured source flux and its half-light radius. We have performed photometry for {approx}73,000 unique objects; approximately one-half of our detections are brighter than the 10{sigma} point-source detection limit at F814W = 25.8 mag (AB). The slight majority of objects (60%) are unresolved or only marginally resolved by ACS. We estimate that Coma members are 5%-10% of all source detections, which consist of a large population of unresolved compact sources (primarily globular clusters but also ultra-compact dwarf galaxies) and a wide variety of extended galaxies from a cD galaxy to dwarf low surface brightness galaxies. The red sequence of Coma member galaxies has a color-magnitude relation with a constant slope and dispersion over 9 mag (-21 < M {sub F814W} < -13). The initial data release for the HST-ACS Coma Treasury program was made available to the public in 2008

  10. Comparative assessment of TRU waste forms and processes. Volume II. Waste form data, process descriptions, and costs.

    SciTech Connect (OSTI)

    Ross, W.A.; Lokken, R.O.; May, R.P.; Roberts, F.P.; Thornhill, R.E.; Timmerman, C.L.; Treat, R.L.; Westsik, J.H. Jr.

    1982-09-01

    This volume contains supporting information for the comparative assessment of the transuranic waste forms and processes summarized in Volume I. Detailed data on the characterization of the waste forms selected for the assessment, process descriptions, and cost information are provided. The purpose of this volume is to provide additional information that may be useful when using the data in Volume I and to provide greater detail on particular waste forms and processes. Volume II is divided into two sections and two appendixes. The first section provides information on the preparation of the waste form specimens used in this study and additional characterization data in support of that in Volume I. The second section includes detailed process descriptions for the eight processes evaluated. Appendix A lists the results of MCC-1 leach test and Appendix B lists additional cost data. 56 figures, 12 tables.

  11. Hydrodynamic description of an unmagnetized plasma with multiple ion species. II. Two and three ion species plasmas

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

    Simakov, Andrei Nikolaevich; Molvig, Kim

    2016-03-17

    Paper I [A. N. Simakov and K. Molvig, Phys. Plasmas23, 032115 (2016)] obtained a fluid description for an unmagnetized collisional plasma with multiple ion species. To evaluate collisional plasmatransport fluxes, required for such a description, two linear systems of equations need to be solved to obtain corresponding transport coefficients. In general, this should be done numerically. Herein, the general formalism is used to obtain analytical expressions for such fluxes for several specific cases of interest: a deuterium-tritium plasma; a plasma containing two ion species with strongly disparate masses, which agrees with previously obtained results; and a three ion species plasmamore » made of deuterium, tritium, and gold. We find that these results can be used for understanding the behavior of the aforementioned plasmas, or for verifying a code implementation of the general multi-ion formalism.« less

  12. Tokamak Physics EXperiment (TPX): Toroidal field magnet design, development and manufacture. SDRL 15, System design description. Volume 1

    SciTech Connect (OSTI)

    1995-09-22

    This System Design Description, prepared in accordance with the TPX Project Management Plan provides a summary or TF Magnet System design features at the conclusion of Phase I, Preliminary Design and Manufacturing Research. The document includes the analytical and experimental bases for the design, and plans for implementation in final design, manufacturing, test, and magnet integration into the tokamak. Requirements for operation and maintenance are outlined, and references to sources of additional information are provided.

  13. Nuclear-fuel-cycle risk assessment: descriptions of representative non-reactor facilities. Sections 1-14

    SciTech Connect (OSTI)

    Schneider, K.J.

    1982-09-01

    The Fuel Cycle Risk Assessment Program was initiated to provide risk assessment methods for assistance in the regulatory process for nuclear fuel cycle facilities other than reactors. This report, the first from the program, defines and describes fuel cycle elements that are being considered in the program. One type of facility (and in some cases two) is described that is representative of each element of the fuel cycle. The descriptions are based on real industrial-scale facilities that are current state-of-the-art, or on conceptual facilities where none now exist. Each representative fuel cycle facility is assumed to be located on the appropriate one of four hypothetical but representative sites described. The fuel cycles considered are for Light Water Reactors with once-through flow of spent fuel, and with plutonium and uranium recycle. Representative facilities for the following fuel cycle elements are described for uranium (or uranium plus plutonium where appropriate): mining, milling, conversion, enrichment, fuel fabrication, mixed-oxide fuel refabrication, fuel reprocessing, spent fuel storage, high-level waste storage, transuranic waste storage, spent fuel and high-level and transuranic waste disposal, low-level and intermediate-level waste disposal, and transportation. For each representative facility the description includes: mainline process, effluent processing and waste management, facility and hardware description, safety-related information and potential alternative concepts for that fuel cycle element. The emphasis of the descriptive material is on safety-related information. This includes: operating and maintenance requirements, input/output of major materials, identification and inventories of hazardous materials (particularly radioactive materials), unit operations involved, potential accident driving forces, containment and shielding, and degree of hands-on operation.

  14. Dynamical description of the moments of the energy distribution of fission fragments and scission of a fissile nucleus

    SciTech Connect (OSTI)

    Borunov, M. V., E-mail: bmv@opsb.ru; Nadtochy, P. N.; Adeev, G. D. [Omsk State University (Russian Federation)

    2007-11-15

    A multidimensional stochastic approach to fission dynamics on the basis of three-dimensional Langevin equations is applied systematically to calculating the first four moments of the energy distribution of fission fragments over a broad range of Coulomb parameter values (700 < Z{sup 2}/A{sup 1/3} < 1700). For the scission of a fissile nucleus into fragments, use was made of various criteria traditional in modern fission theory: the vanishing of the neck radius at the scission instant and the equality of the neck radius to about 0.3R{sub 0} at this instant. In calculating the energy distribution, both of the criteria used lead to a fairly good description of experimental data on the first two moments and to a satisfactory description of data on the third and fourth moments of the distribution. However, the quality of the description of available experimental data is insufficiently good for giving preference to any of these criteria. Within three-dimensional Langevin dynamics, it is shown that the vanishing-radius criterion leads to unexpectably good agreement with experimental data on the first four moments of the energy distribution. A modified version of one-body dissipation where the coefficient that takes into account the reduction of the wall-formula contribution was set to k{sub s} = 0.25 was used in the calculations.

  15. Description of the dipole giant resonance in heavy and superheavy nuclei within Skyrme random-phase approximation

    SciTech Connect (OSTI)

    Kleinig, W.; Nesterenko, V. O.; Kvasil, J.; Vesely, P.; Reinhard, P.-G.

    2008-10-15

    The E1(T=1) isovector dipole giant resonance (GDR) in heavy and superheavy deformed nuclei is analyzed over a sample of 18 rare-earth nuclei, four actinides, and three chains of superheavy elements (Z=102, 114, and 120). The basis of the description is the self-consistent separable random-phase approximation (SRPA) using the Skyrme force SLy6. The model well reproduces the experimental data in the rare-earth and actinide regions. The trend of the resonance peak energies follows the estimates from collective models, showing a bias to the volume mode for the rare-earth isotopes and a mix of volume and surface modes for actinides and superheavy elements. The widths of the GDR are mainly determined by the Landau fragmentation, which in turn is found to be strongly influenced by deformation. A deformation splitting of the GDR can contribute to about one-third of the width, and about 1 MeV further broadening can be associated with mechanisms beyond the SRPA description (e.g., escape widths and coupling with complex configurations)

  16. Configuration interaction singles natural orbitals: An orbital basis for an efficient and size intensive multireference description of electronic excited states

    SciTech Connect (OSTI)

    Shu, Yinan; Levine, Benjamin G.; Hohenstein, Edward G.

    2015-01-14

    Multireference quantum chemical methods, such as the complete active space self-consistent field (CASSCF) method, have long been the state of the art for computing regions of potential energy surfaces (PESs) where complex, multiconfigurational wavefunctions are required, such as near conical intersections. Herein, we present a computationally efficient alternative to the widely used CASSCF method based on a complete active space configuration interaction (CASCI) expansion built from the state-averaged natural orbitals of configuration interaction singles calculations (CISNOs). This CISNO-CASCI approach is shown to predict vertical excitation energies of molecules with closed-shell ground states similar to those predicted by state averaged (SA)-CASSCF in many cases and to provide an excellent reference for a perturbative treatment of dynamic electron correlation. Absolute energies computed at the CISNO-CASCI level are found to be variationally superior, on average, to other CASCI methods. Unlike SA-CASSCF, CISNO-CASCI provides vertical excitation energies which are both size intensive and size consistent, thus suggesting that CISNO-CASCI would be preferable to SA-CASSCF for the study of systems with multiple excitable centers. The fact that SA-CASSCF and some other CASCI methods do not provide a size intensive/consistent description of excited states is attributed to changes in the orbitals that occur upon introduction of non-interacting subsystems. Finally, CISNO-CASCI is found to provide a suitable description of the PES surrounding a biradicaloid conical intersection in ethylene.

  17. The IAEA Coordinated Research Program on HTGR Reactor Physics, Thermal-hydraulics and Depletion Uncertainty Analysis: Description of the Benchmark Test Cases and Phases

    SciTech Connect (OSTI)

    Frederik Reitsma; Gerhard Strydom; Bismark Tyobeka; Kostadin Ivanov

    2012-10-01

    The continued development of High Temperature Gas Cooled Reactors (HTGRs) requires verification of design and safety features with reliable high fidelity physics models and robust, efficient, and accurate codes. The uncertainties in the HTR analysis tools are today typically assessed with sensitivity analysis and then a few important input uncertainties (typically based on a PIRT process) are varied in the analysis to find a spread in the parameter of importance. However, one wish to apply a more fundamental approach to determine the predictive capability and accuracies of coupled neutronics/thermal-hydraulics and depletion simulations used for reactor design and safety assessment. Today there is a broader acceptance of the use of uncertainty analysis even in safety studies and it has been accepted by regulators in some cases to replace the traditional conservative analysis. Finally, there is also a renewed focus in supplying reliable covariance data (nuclear data uncertainties) that can then be used in uncertainty methods. Uncertainty and sensitivity studies are therefore becoming an essential component of any significant effort in data and simulation improvement. In order to address uncertainty in analysis and methods in the HTGR community the IAEA launched a Coordinated Research Project (CRP) on the HTGR Uncertainty Analysis in Modelling early in 2012. The project is built on the experience of the OECD/NEA Light Water Reactor (LWR) Uncertainty Analysis in Best-Estimate Modelling (UAM) benchmark activity, but focuses specifically on the peculiarities of HTGR designs and its simulation requirements. Two benchmark problems were defined with the prismatic type design represented by the MHTGR-350 design from General Atomics (GA) while a 250 MW modular pebble bed design, similar to the INET (China) and indirect-cycle PBMR (South Africa) designs are also included. In the paper more detail on the benchmark cases, the different specific phases and tasks and the latest

  18. U-AVLIS feed conversion using continuous metallothermic reduction of UF{sub 4}: System description and cost estimate

    SciTech Connect (OSTI)

    Not Available

    1994-04-01

    The purpose of this document is to present a system description and develop baseline capital and operating cost estimates for commercial facilities which produced U-Fe feedstock for AVLIS enrichment plants using the continuous fluoride reduction (CFR) process. These costs can then be used together with appropriate economic assumptions to calculate estimated unit costs to the AVLIS plant owner (or utility customer) for such conversion services. Six cases are being examined. All cases assume that the conversion services are performed by a private company at a commercial site which has an existing NRC license to possess source material and which has existing uranium processing operations. The cases differ in terms of annual production capacity and whether the new process system is installed in a new building or in an existing building on the site. The six cases are summarized here.

  19. Nuclear-fuel-cycle risk assessment: descriptions of representative non-reactor facilities, Sections 15-19

    SciTech Connect (OSTI)

    Schneider, K.J.

    1982-09-01

    Information is presented under the following section headings: fuel reprocessing; spent fuel and high-level and transuranic waste storage; spent fuel and high-level and transuranic waste disposal; low-level and intermediate-level waste disposal; and, transportation of radioactive materials in the nuclear fuel cycle. In each of the first three sections a description is given on the mainline process, effluent processing and waste management systems, plant layout, and alternative process schemes. Safety information and a summary are also included in each. The section on transport of radioactive materials includes information on the transportation of uranium ore, uranium ore concentrate, UF/sub 6/, PuO/sub 2/ powder, unirradiated uranium and mixed-oxide fuel assemblies, spent fuel, solidified high-level waste, contact-handled transuranic waste, remote-handled transuranic waste, and low and intermediate level nontransuranic waste. A glossary is included. (JGB)

  20. Accurate description of torsion potentials in conjugated polymers using density functionals with reduced self-interaction error

    SciTech Connect (OSTI)

    Sutton, Christopher; Gray, Matthew T.; Brunsfeld, Max; Parrish, Robert M.; Sherrill, C. David; Sears, John S.; Brédas, Jean-Luc E-mail: thomas.koerzdoerfer@uni-potsdam.de; Körzdörfer, Thomas E-mail: thomas.koerzdoerfer@uni-potsdam.de; Computational Chemistry, Institute of Chemistry, University of Potsdam, D-14476 Potsdam

    2014-02-07

    We investigate the torsion potentials in two prototypical π-conjugated polymers, polyacetylene and polydiacetylene, as a function of chain length using different flavors of density functional theory. Our study provides a quantitative analysis of the delocalization error in standard semilocal and hybrid density functionals and demonstrates how it can influence structural and thermodynamic properties. The delocalization error is quantified by evaluating the many-electron self-interaction error (MESIE) for fractional electron numbers, which allows us to establish a direct connection between the MESIE and the error in the torsion barriers. The use of non-empirically tuned long-range corrected hybrid functionals results in a very significant reduction of the MESIE and leads to an improved description of torsion barrier heights. In addition, we demonstrate how our analysis allows the determination of the effective conjugation length in polyacetylene and polydiacetylene chains.

  1. Nonequilibrium critical relaxation of structurally disordered systems in the short-time regime: Renormalization group description and computer simulation

    SciTech Connect (OSTI)

    Prudnikov, V. V. Prudnikov, P. V.; Kalashnikov, I. A.; Rychkov, M. V.

    2010-02-15

    The influence of nonequilibrium initial states on the evolution of anisotropic systems with quenched uncorrelated structural defects at the critical point is studied. The field-theoretical description of the nonequilibrium critical behavior of 3D systems is obtained for the first time, and the dynamic critical exponent of the short-time evolution in the two-loop approximation without the use of {epsilon} expansion is calculated. The values of dynamic critical exponents calculated using the series resummation methods are compared with the results of computer simulation of nonequilibrium critical behavior of the 3D disordered Ising model in the short-time regime. It is demonstrated that the values of the critical exponents calculated in this paper are in better agreement with the results of computer simulation than the results of application of {epsilon} expansion.

  2. Modeling of fluidized-bed combustion of coal: Phase II, final reports. Volume II. Detailed description of the model

    SciTech Connect (OSTI)

    Louis, J.F.; Tung, S.E.

    1980-10-01

    This document is the second of a seven volume series of our Phase II Final Report. This volume deals with detailed descriptions of the structure of each program member (subroutines and functions), the interrelation between the members of a submodel, and the interrelation between the various submodels as such. The systems model for fluidized bed combustors (FBC-II) consists of a systematic combination of the following interrelated areas: fluid mechanics and bubble growth, char combustion and associated kinetics for particle burnout, sulfur capture, NO/sub x/ formation and reduction, freeboard reactions, and heat transfer. Program outline is shown in Figure 1.1. Input variables (supplied by the user are inspected to check that they lie inside the allowed range of values and are input to the various routines as needed. The necessary physical and fluid mechanical properties are calculated and utilized in estimating char combustion and sulfur capture in the bed and the freeboard. NO/sub x/ and CO emissions are estimated by taking into account all relevant chemical reactions. A material and energy balance is made over the bed. Figure 1.1 shows a block diagram of the systems program. In this diagram, the overall structure of the FBC program is illustrated in terms of the various submodels that together constitute the systems program. A more detailed outline of the systems program is shown in Figure 1.2. In this figure, all important subroutine members of the FBC program are shown, and their linkage to each other, as well as to the main program is indicated. A description of the exact sequence in which these various routines are called at time of program execution is provided in Chapter 8 under the executive routine MAIN.

  3. Baseline tests for arc melter vitrification of INEL buried wastes. Volume 1: Facility description and summary data report

    SciTech Connect (OSTI)

    Oden, L.L.; O`Connor, W.K.; Turner, P.C.; Soelberg, N.R.; Anderson, G.L.

    1993-11-19

    This report presents field results and raw data from the Buried Waste Integrated Demonstration (BWID) Arc Melter Vitrification Project Phase 1 baseline test series conducted by the Idaho National Engineering Laboratory (INEL) in cooperation with the U.S. Bureau of Mines (USBM). The baseline test series was conducted using the electric arc melter facility at the USBM Albany Research Center in Albany, Oregon. Five different surrogate waste feed mixtures were tested that simulated thermally-oxidized, buried, TRU-contaminated, mixed wastes and soils present at the INEL. The USBM Arc Furnace Integrated Waste Processing Test Facility includes a continuous feed system, the arc melting furnace, an offgas control system, and utilities. The melter is a sealed, 3-phase alternating current (ac) furnace approximately 2 m high and 1.3 m wide. The furnace has a capacity of 1 metric ton of steel and can process as much as 1,500 lb/h of soil-type waste materials. The surrogate feed materials included five mixtures designed to simulate incinerated TRU-contaminated buried waste materials mixed with INEL soil. Process samples, melter system operations data and offgas composition data were obtained during the baseline tests to evaluate the melter performance and meet test objectives. Samples and data gathered during this program included (a) automatically and manually logged melter systems operations data, (b) process samples of slag, metal and fume solids, and (c) offgas composition, temperature, velocity, flowrate, moisture content, particulate loading and metals content. This report consists of 2 volumes: Volume I summarizes the baseline test operations. It includes an executive summary, system and facility description, review of the surrogate waste mixtures, and a description of the baseline test activities, measurements, and sample collection. Volume II contains the raw test data and sample analyses from samples collected during the baseline tests.

  4. DESCRIPTION OF THE TRITIUM-PRODUCING BURNABLE ABSORBER ROD FOR THE COMMERCIAL LIGHT WATER REACTOR TTQP-1-015 Rev 19

    SciTech Connect (OSTI)

    Burns, Kimberly A.; Love, Edward F.; Thornhill, Cheryl K.

    2012-02-01

    Tritium-producing burnable absorber rods (TPBARs) used in the U.S. Department of Energy’s Tritium Readiness Program are designed to produce tritium when placed in a Westinghouse or Framatome 17x17 fuel assembly and irradiated in a pressurized water reactor (PWR). This document provides an unclassified description of the current design baseline for the TPBARs. This design baseline is currently valid only for Watts Bar reactor production cores. A description of the Lead Use TPBARs will not be covered in the text of the document, but the applicable drawings, specifications and test plan will be included in the appropriate appendices.

  5. PARS II Course Descriptions

    Broader source: Energy.gov [DOE]

    Sign up for PARS 102 or PARS 103, depending on your project assessment role and function.  PARS 104 will be offered to site contractors as part of Dekker's Contractor deployment training.

  6. Detailed Course Module Description

    Broader source: Energy.gov [DOE]

    This document lists the course modules for building science courses offered at Cornell's Collaborator Sustainable Buildingi Practice course.

  7. Paducah Site Description

    Broader source: Energy.gov [DOE]

    The Paducah Gaseous Diffusion (PGDP) Site is located in McCracken County, Kentucky, 10 miles west of the city of Paducah.  

  8. Portsmouth Site Description

    Broader source: Energy.gov [DOE]

    The Portsmouth site is in rural Pike County, Ohio, north of the city of Portsmouth. It is located on a federal reservation that encompasses 3,777 acres. The site employs more than 2,000 workers, making it one of the largest employers in the region. It consists of three operational areas: the gaseous diffusion plant, centrifuge facility and depleted uranium hexafluoride conversion facility.

  9. Description of Detailed Tables

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

    for the 1999 Commercial Buildings Energy Consumption Survey (CBECS) consists of building characteristics tables B1 through B39, which contain the number of buildings and...

  10. AREST model description

    SciTech Connect (OSTI)

    Engel, D.W.; McGrail, B.P.

    1993-11-01

    The Office of Civilian Radioactive Waste Management and the Power Reactor and Nuclear Fuel Development Corporation of Japan (PNC) have supported the development of the Analytical Repository Source-Term (AREST) at Pacific Northwest Laboratory. AREST is a computer model developed to evaluate radionuclide release from an underground geologic repository. The AREST code can be used to calculate/estimate the amount and rate of each radionuclide that is released from the engineered barrier system (EBS) of the repository. The EBS is the man-made or disrupted area of the repository. AREST was designed as a system-level models to simulate the behavior of the total repository by combining process-level models for the release from an individual waste package or container. AREST contains primarily analytical models for calculating the release/transport of radionuclides to the lost rock that surrounds each waste package. Analytical models were used because of the small computational overhead that allows all the input parameters to be derived from a statistical distribution. Recently, a one-dimensional numerical model was also incorporated into AREST, to allow for more detailed modeling of the transport process with arbitrary length decay chains. The next step in modeling the EBS, is to develop a model that couples the probabilistic capabilities of AREST with a more detailed process model. This model will need to look at the reactive coupling of the processes that are involved with the release process. Such coupling would include: (1) the dissolution of the waste form, (2) the geochemical modeling of the groundwater, (3) the corrosion of the container overpacking, and (4) the backfill material, just to name a few. Several of these coupled processes are already incorporated in the current version of AREST.

  11. Plan Descriptions & Summaries

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

    high-efficiency perovskite solar cells Researchers reveal a new solution-based hot-casting technique that allows growth of highly efficient and reproducible solar cells from...

  12. ARM - Detailed Experiment Description

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

    active research and is one of the main themes of research associated with the tropical western Pacific ARM sites located in Manus (Papua New Guinea), Nauru, and Darwin (Australia). ...

  13. Description of Proposed Action

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

    contained within the WIPP Land Withdrawal Area as part of ... petroleumnatural gas products that pre-exist in ... the other regulatory requirements set forth above are ...

  14. Description of Chart

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

    Restructuring by State Map. State: 51 items, 51 with data. Alabama is 0. Value is in the Not Active range, Alabama Deregulation: NO Retail Choice: NO Click for more information (State Restructuring Activities: None since 10/2000), Detail for AL. Arkansas is 9. Value is in the Suspended range, Arkansas Deregulation: SUSPENDED Retail Choice: NO Click for more information (State Restructuring Activities: None since 03/2003), Detail for AR. Arizona is 9. Value is in the Suspended range, Arizona

  15. Supercomputing Challenge Program Description

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

    | National Nuclear Security Administration | (NNSA) Supercomputers and New Mexico students collide in NNSA-sponsored challenge Wednesday, May 11, 2016 - 10:27am World-class science, technology, and engineering enables NNSA's missions. It's no surprise, then, that our labs and sites support STEM education initiatives ranging from preschool programs to graduate fellowships. Most recently, shining stars of New Mexico schools joined the more than 10,000 students who have gone head-to-head in the

  16. Supercomputing Challenge Program Description

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

    program that teaches mid school and high school students how to use powerful computers to model real-world problems and to explore computational approaches to their...

  17. Detailed Course Module Description

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

    flow o Show capillary effect of wood, concrete and glass o Discuss moisture storage of ... hurricane-resistance, wind, fire, corrosion and other climate-specific factors that ...

  18. Job Code Description Hourly Wage TR-I Job Code TR I Wage TR-II Job

    National Nuclear Security Administration (NNSA)

    Wage TR-I Job Code TR I Wage TR-II Job Code TR II Wage TR-III Job Code TR III Wage Job Code Description Hourly Wage TR-I Job Code TR I Wage TR-II Job Code TR II Wage TR-III Job Code TR III Wage 56-HOUR TOUR Hourly Premiums TR-I 0.25 TR-II $0.50 TR-III $0.75 10-HOUR SHIFT Hourly Premiums TR-I $0.45 TR-II $0.90 TR-III $1.35 CIC $0.60 CIC $1.08 HAZ $0.81 HAZ $1.46 UD/BA $0.25 UD/BA $0.45 ELF $0.30 ELF $0.54 TR-I $0.25 TR-I $0.45 TR-II $0.50 TR-II $0.90 TR-III $0.75 TR-III $1.35 021450 Entry-Level

  19. Unified description of 6Li structure and deuterium-4He dynamics with chiral two- and three-nucleon forces

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

    Hupin, Guillaume; Quaglioni, Sofia; Navratil, Petr

    2015-05-29

    Here, we provide a unified ab initio description of the 6Li ground state and elastic scattering of deuterium (d) on 4He (α) using two- and three-nucleon forces from chiral effective field theory. We analyze the influence of the three-nucleon force and reveal the role of continuum degrees of freedom in shaping the low-lying spectrum of 6Li. The calculation reproduces the empirical binding energy of 6Li, yielding an asymptotic D- to S-state ratio of the 6Li wave function in the d+α configuration of –0.027, in agreement with a determination from 6Li–4He elastic scattering, but overestimates the excitation energy of the 3+more » state by 350 keV. The bulk of the computed differential cross section is in good agreement with data. These results endorse the application of the present approach to the evaluation of the 2H(α,γ)6Li radiative capture, responsible for the big-bang nucleosynthesis of 6Li.« less

  20. Modeling Excited States in TiO2 Nanoparticles: On the Accuracy of a TD-DFT Based Description

    SciTech Connect (OSTI)

    Berardo, Enrico; Hu, Hanshi; Shevlin, S. A.; Woodley, Scott M.; Kowalski, Karol; Zwijnenburg, Martijn A.

    2014-03-11

    We have investigated the suitability of Time-Dependent Density Functional Theory (TD-DFT) to describe vertical low-energy excitations in naked and hydrated titanium dioxide nanoparticles through a comparison with results from Equation-of-Motion Coupled Cluster (EOM-CC) quantum chemistry methods. We demonstrate that for most TiO2 nanoparticles TD-DFT calculations with commonly used exchange-correlation (XC-)potentials (e.g. B3LYP) and EOM-CC methods give qualitatively similar results. Importantly, however, we also show that for an important subset of structures, TD-DFT gives qualitatively different results depending upon the XC-potential used and that in this case only TD-CAM-B3LYP and TD-BHLYP calculations yield results that are consistent with those obtained using EOM-CC theory. Moreover, we demonstrate that the discrepancies for such structures arise from a particular combination of defects, excitations involving which are charge-transfer excitations and hence are poorly described by XC-potentials that contain no or low fractions of Hartree-Fock like exchange. Finally, we discuss that such defects are readily healed in the presence of ubiquitously present water and that as a result the description of vertical low-energy excitations for hydrated TiO2 nanoparticles is hence non-problematic.

  1. MHD advanced power train. Phase 1, Final report: Volume 3, Power train system description and specification for 200MWe Plant

    SciTech Connect (OSTI)

    Jones, A.R.

    1985-08-01

    This System Design Description and Specification provides the basis for the design of the magnetohydrodynamic (MHD) Power Train (PT) for a nominal 200 MWe early commercial tiHD/Steam Power Plant. This document has been developed under Task 2, Conceptual Design, of Contract DE-AC22-83PC60575 and is to be used by the project as the controlling and coordinating documentation during future design efforts. Modification and revision of this specification will occur as the design matures, and tiie-Westinghouse MHD Project Manager will be the focal point for maintaining this document and issuing periodic revisions. This document is intended to delineate the power train and-power train components requirements and assumptions that properly reflect the MHD/Steam Power Plant in the PT design. The parameters discussed in this document have been established through system calculations as well as through constraints set by technology and by limitations on materials, cost, physical processes associated with MHD, and the expected operating data for the plant. The specifications listed in this document have precedence over all referenced documents. Where this specification appears to conflict with the requirements of a reference document, such conflicts should be brought to the attention of the Westinghouse MHD Project Manager for resolution.

  2. Description of the stand-damage model: Part of the gypsy moth life system model. Forest Service general technical report (Final)

    SciTech Connect (OSTI)

    Colbert, J.J.; Sheehan, K.A.

    1995-08-16

    This document describes the structure, organization, and mathematical formulations for the Stand-Damage Model and the Biological basis for these formulations. Growth, mortality, and regeneration are modeled along with the effects of user-prescribed defoliation and stand-management actions. The appendices provide a full description of the logic and mathematics in the form of code listings, structure charts, and files.

  3. Description and Evaluation of Tropospheric Chemistry and Aerosols in the Community Earth System Model (CESM1.2)

    SciTech Connect (OSTI)

    Tilmes, S.; Lamarque, J.-F.; Emmons, L.; Kinnison, Douglas E.; Ma, Po-Lun; Liu, Xiaohong; Ghan, Steven J.; Bardeen, C.; Arnold, S.; Deeter, M.; Vitt, Francis; Ryerson, T. B.; Elkins, J. W.; Moore, F.; Spackman, R.; Martin, M. V.

    2015-01-01

    The Community Atmosphere Model (CAM), version 5, is now coupled to extensive tropospheric and stratospheric chemistry, called CAM5-chem, and is available in addition to CAM4-chem in the Community Earth System Model (CESM) version 1.2. Both configurations are well suited as tools for atmospheric-chemistry modeling studies in the troposphere and lower stratosphere, whether with internally derived free running (FR) meteorology, or specified dynamics (SD). The main focus of this paper is to compare the performance of these configurations against observations from surface, aircraft, and satellite, as well as understand the origin of the identified differences. We particularly focus on comparing present-day methane lifetime estimates within the different model configurations, which range between 7.8 years in the SD configuration of CAM5-chem and 8.8 years in the FR configuration of CAM4-chem. We find that tropospheric surface area density is an important factor in controlling the burden of the hydroxyl radical (OH), which causes differences in tropical methane lifetime of about half a year between CAM4-chem and CAM5-chem. In addition, different distributions of nitrogen oxides (NOx) produced from lightning production explain about half of the difference between SD and FR model versions in both CAM4-chem and CAM5-chem. Remaining differences in the tropical OH burden are due to enhanced tropical ozone burden in SD configurations compared to the FR versions, which are not only caused by differences in chemical production or loss, but also by transport and mixing. For future studies, we recommend the use of CAM5-chem, due to improved aerosol description and inclusion of aerosol-cloud interactions. However, smaller tropospheric surface area density in the current version of CAM5-chem compared to CAM4-chem results in larger oxidizing capacity in the troposphere and therefore a shorter methane lifetime.

  4. Description and Evaluation of Tropospheric Chemistry and Aerosols in the Community Earth System Model (CESM1.2)

    SciTech Connect (OSTI)

    Tilmes, S.; Lamarque, J. -F.; Emmons, L.; Kinnison, Douglas E.; Ma, Po-Lun; Liu, Xiaohong; Ghan, Steven J.; Bardeen, C.; Arnold, S.; Deeter, M.; Vitt, Francis; Ryerson, T. B.; Elkins, J. W.; Moore, F.; Spackman, R.; Martin, M. V.

    2015-05-13

    The Community Atmosphere Model (CAM), version 5, is now coupled to extensive tropospheric and stratospheric chemistry, called CAM5-chem, and is available in addition to CAM4-chem in the Community Earth System Model (CESM) version 1.2. Both configurations are well suited as tools for atmospheric-chemistry modeling studies in the troposphere and lower stratosphere, whether with internally derived “free running” (FR) meteorology, or “specified dynamics” (SD). The main focus of this paper is to compare the performance of these configurations against observations from surface, aircraft, and satellite, as well as understand the origin of the identified differences. We particularly focus on comparing present-day methane lifetime estimates within the different model configurations, which range between 7.8 years in the SD configuration of CAM5-chem and 8.8 years in the FR configuration of CAM4-chem. We find that tropospheric surface area density is an important factor in controlling the burden of the hydroxyl radical (OH), which causes differences in tropical methane lifetime of about half a year between CAM4-chem and CAM5-chem. In addition, different distributions of nitrogen oxides (NOx) produced from lightning production explain about half of the difference between SD and FR model versions in both CAM4-chem and CAM5-chem. Remaining differences in the tropical OH burden are due to enhanced tropical ozone burden in SD configurations compared to the FR versions, which are not only caused by differences in chemical production or loss, but also by transport and mixing. For future studies, we recommend the use of CAM5-chem, due to improved aerosol description and inclusion of aerosol-cloud interactions. However, smaller tropospheric surface area density in the current version of CAM5-chem compared to CAM4-chem results in larger oxidizing capacity in the troposphere and therefore a shorter methane lifetime.

  5. Description and Evaluation of Tropospheric Chemistry and Aerosols in the Community Earth System Model (CESM1.2)

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

    Tilmes, S.; Lamarque, J. -F.; Emmons, L.; Kinnison, Douglas E.; Ma, Po-Lun; Liu, Xiaohong; Ghan, Steven J.; Bardeen, C.; Arnold, S.; Deeter, M.; et al

    2015-05-13

    The Community Atmosphere Model (CAM), version 5, is now coupled to extensive tropospheric and stratospheric chemistry, called CAM5-chem, and is available in addition to CAM4-chem in the Community Earth System Model (CESM) version 1.2. Both configurations are well suited as tools for atmospheric-chemistry modeling studies in the troposphere and lower stratosphere, whether with internally derived “free running” (FR) meteorology, or “specified dynamics” (SD). The main focus of this paper is to compare the performance of these configurations against observations from surface, aircraft, and satellite, as well as understand the origin of the identified differences. We particularly focus on comparing present-daymore » methane lifetime estimates within the different model configurations, which range between 7.8 years in the SD configuration of CAM5-chem and 8.8 years in the FR configuration of CAM4-chem. We find that tropospheric surface area density is an important factor in controlling the burden of the hydroxyl radical (OH), which causes differences in tropical methane lifetime of about half a year between CAM4-chem and CAM5-chem. In addition, different distributions of nitrogen oxides (NOx) produced from lightning production explain about half of the difference between SD and FR model versions in both CAM4-chem and CAM5-chem. Remaining differences in the tropical OH burden are due to enhanced tropical ozone burden in SD configurations compared to the FR versions, which are not only caused by differences in chemical production or loss, but also by transport and mixing. For future studies, we recommend the use of CAM5-chem, due to improved aerosol description and inclusion of aerosol-cloud interactions. However, smaller tropospheric surface area density in the current version of CAM5-chem compared to CAM4-chem results in larger oxidizing capacity in the troposphere and therefore a shorter methane lifetime.« less

  6. Descriptions and diagrams of the primary and annulus ventilation systems of the double-shell tank farms as of January 1988

    SciTech Connect (OSTI)

    Blackman, A.E.; Waters, E.D.

    1994-12-28

    This document is a compilation of information describing the ventilation systems of the Double-Shell Tank farms (214-AN, -AP, -AW, -AW, -AY, -AZ, and -SY). A general description of the primary tank and annulus ventilation systems is given along with specific information on the high efficiency particulate air (HEPA) filters, condensers, preheaters, exhaust fans, and piping. This information is considered to be current as of January 1988. 38 refs, 20 figs, 30 tabs.

  7. Environmental site description for a Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) production plant at the Oak Ridge Gaseous Diffusion Plant Site

    SciTech Connect (OSTI)

    Not Available

    1991-09-01

    In January 1990, the Secretary of Energy approved a plan for the demonstration and deployment of the Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) technology, with the near-term goal to provide the necessary information to make a deployment decision by November 1992. The U-AVLIS process is based on electrostatic extraction of photoionized U-235 atoms from an atomic vapor stream created by electron-beam vaporization of uranium metal alloy. A programmatic document for use in screening DOE sites to locate the U-AVLIS production plant was developed and implemented in two parts (Wolsko et al. 1991). The first part consisted of a series of screening analyses, based on exclusionary and other criteria, that identified a reasonable number of candidate sites. These sites were then subjected to a more rigorous and detailed comparative analysis for the purpose of developing a short list of reasonable alternative sites for later environmental examination. This environmental site description (ESD) provides a detailed description of the ORGDP site and vicinity suitable for use in an environmental impact statement (EIS). The report is based on existing literature, data collected at the site, and information collected by Argonne National Laboratory (ANL) staff during a site visit. The organization of the ESD is as follows. Topics addressed in Sec. 2 include a general site description and the disciplines of geology, water resources, biotic resources, air resources, noise, cultural resources, land use, socioeconomics, and waste management. Identification of any additional data that would be required for an EIS is presented in Sec. 3. Following the site description and additional data requirements, Sec. 4 provides a short, qualitative assessment of potential environmental issues. 37 refs., 20 figs., 18 tabs.

  8. Benin: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    MWhyear 100 2008 NREL Coal Reserves Unavailable Million Short Tons NA 2008 EIA Natural Gas Reserves 1,133,000,000 Cubic Meters (cu m) 97 2010 CIA World Factbook Oil Reserves...

  9. Ghana: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    MWhyear 73 2008 NREL Coal Reserves Unavailable Million Short Tons NA 2008 EIA Natural Gas Reserves 22,650,000,000 Cubic Meters (cu m) 76 2010 CIA World Factbook Oil Reserves...

  10. Vietnam: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    MWhyear 66 2008 NREL Coal Reserves 165.35 Million Short Tons 53 2008 EIA Natural Gas Reserves 680,000,000,000 Cubic Meters (cu m) 31 2010 CIA World Factbook Oil Reserves...

  11. Senegal: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    MWhyear 76 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 0...

  12. United States: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    MWhyear 6 2008 NREL Coal Reserves 260,551.00 Million Short Tons 1 2008 EIA Natural Gas Reserves 6,928,000,000,000 Cubic Meters (cu m) 6 2010 CIA World Factbook Oil...

  13. Reference Shelf

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

    The National Academies Science Daily New Scientist SciCentral Statistics American FactFinder CIA World Factbook Data.gov FedStats Los Alamos County QuickFacts from the U.S. Census ...

  14. Germany: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    276,000,000 Barrels (bbl) 54 2010 CIA World Factbook Energy Maps featuring Germany PV Solar Resource: U.S., Germany and Spain PV Solar Resource - US, Spain and Germany Germany...

  15. Mali: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    CIA World Factbook, Appendix D Reegle Clean Energy Datasets Mali is a country in Africa. External Links Mali Renewable Energy Data from IEA Mali Contacts from Climate-Eval...

  16. Kazakhstan: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    MWhyear 14 2008 NREL Coal Reserves 37,037.66 Million Short Tons 8 2008 EIA Natural Gas Reserves 2,407,000,000,000 Cubic Meters (cu m) 15 2010 CIA World Factbook Oil Reserves...

  17. South Africa: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    MWhyear 23 2008 NREL Coal Reserves 33,241.30 Million Short Tons 9 2008 EIA Natural Gas Reserves 27,160,000 Cubic Meters (cu m) 102 2010 CIA World Factbook Oil Reserves...

  18. Chile: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    MWhyear 43 2008 NREL Coal Reserves 170.86 Million Short Tons 52 2008 EIA Natural Gas Reserves 97,970,000,000 Cubic Meters (cu m) 53 2010 CIA World Factbook Oil Reserves...

  19. Denmark: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    MWhyear 143 2008 NREL Coal Reserves Unavailable Million Short Tons NA 2008 EIA Natural Gas Reserves 61,300,000,000 Cubic Meters (cu m) 62 2010 CIA World Factbook Oil Reserves...

  20. Netherlands: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    MWhyear 151 2008 NREL Coal Reserves Unavailable Million Short Tons NA 2008 EIA Natural Gas Reserves 1,416,000,000,000 Cubic Meters (cu m) 24 2010 CIA World Factbook Oil Reserves...

  1. Nigeria: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    MWhyear 35 2008 NREL Coal Reserves 209.44 Million Short Tons 49 2008 EIA Natural Gas Reserves 5,246,000,000,000 Cubic Meters (cu m) 8 2010 CIA World Factbook Oil Reserves...

  2. Turkey: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    MWhyear 39 2008 NREL Coal Reserves 2,582.72 Million Short Tons 20 2008 EIA Natural Gas Reserves 6,088,000,000 Cubic Meters (cu m) NA 2010 CIA World Factbook Oil Reserves...

  3. India: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    MWhyear 8 2008 NREL Coal Reserves 66,800.07 Million Short Tons 5 2008 EIA Natural Gas Reserves 1,075,000,000,000 Cubic Meters (cu m) 26 2010 CIA World Factbook Oil Reserves...

  4. Indonesia: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    MWhyear 18 2008 NREL Coal Reserves 6,094.68 Million Short Tons 14 2008 EIA Natural Gas Reserves 3,001,000,000,000 Cubic Meters (cu m) 14 2010 CIA World Factbook Oil Reserves...

  5. Japan: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    MWhyear 67 2008 NREL Coal Reserves 385.81 Million Short Tons 38 2008 EIA Natural Gas Reserves 20,900,000,000 Cubic Meters (cu m) 77 2010 CIA World Factbook Oil Reserves...

  6. Poland: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    MWhyear 82 2008 NREL Coal Reserves 6,293.10 Million Short Tons 13 2008 EIA Natural Gas Reserves 164,800,000,000 Cubic Meters (cu m) 48 2010 CIA World Factbook Oil Reserves...

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

    Office of Scientific and Technical Information (OSTI)

    is an important step in the code-to-code verification of modern prismatic VHTR codes. ... Country of Publication: United States Language: English Subject: 11 NUCLEAR FUEL CYCLE AND ...

  8. OECD/NEA Burnup Credit Calculational Criticality Benchmark Phase I-B Results

    SciTech Connect (OSTI)

    DeHart, M.D.

    1993-01-01

    Burnup credit is an ongoing technical concern for many countries that operate commercial nuclear power reactors. In a multinational cooperative effort to resolve burnup credit issues, a Burnup Credit Working Group has been formed under the auspices of the Nuclear Energy Agency of the Organization for Economic Cooperation and Development. This working group has established a set of well-defined calculational benchmarks designed to study significant aspects of burnup credit computational methods. These benchmarks are intended to provide a means for the intercomparison of computer codes, methods, and data applied in spent fuel analysis. The benchmarks have been divided into multiple phases, each phase focusing on a particular feature of burnup credit analysis. This report summarizes the results and findings of the Phase I-B benchmark, which was proposed to provide a comparison of the ability of different code systems and data libraries to perform depletion analysis for the prediction of spent fuel isotopic concentrations. Results included here represent 21 different sets of calculations submitted by 16 different organizations worldwide, and are based on a limited set of nuclides determined to have the most important effect on the neutron multiplication factor of light-water-reactor spent fuel. A comparison of all sets of results demonstrates that most methods are in agreement to within 10% in the ability to estimate the spent fuel concentrations of most actinides. All methods are within 11% agreement about the average for all fission products studied. Furthermore, most deviations are less than 10%, and many are less than 5%. The exceptions are {sup 149}Sm, {sup 151}Sm, and {sup 155}Gd.

  9. OECD/NEA burnup credit calculational criticality benchmark Phase I-B results

    SciTech Connect (OSTI)

    DeHart, M.D.; Parks, C.V.; Brady, M.C.

    1996-06-01

    In most countries, criticality analysis of LWR fuel stored in racks and casks has assumed that the fuel is fresh with the maximum allowable initial enrichment. This assumption has led to the design of widely spaced and/or highly poisoned storage and transport arrays. If credit is assumed for fuel burnup, initial enrichment limitations can be raised in existing systems, and more compact and economical arrays can be designed. Such reliance on the reduced reactivity of spent fuel for criticality control is referred to as burnup credit. The Burnup Credit Working Group, formed under the auspices of the Nuclear Energy Agency of the Organization for Economic Cooperation and Development, has established a set of well-defined calculational benchmarks designed to study significant aspects of burnup credit computational methods. These benchmarks are intended to provide a means for the intercomparison of computer codes, methods, and data applied in spent fuel analysis. The benchmarks have been divided into multiple phases, each phase focusing on a particular feature of burnup credit analysis. This report summarizes the results and findings of the Phase I-B benchmark, which was proposed to provide a comparison of the ability of different code systems and data libraries to perform depletion analysis for the prediction of spent fuel isotopic concentrations. Results included here represent 21 different sets of calculations submitted by 16 different organizations worldwide and are based on a limited set of nuclides determined to have the most important effect on the neutron multiplication factor of light-water-reactor spent fuel. A comparison of all sets of results demonstrates that most methods agree to within 10% in the ability to estimate the spent fuel concentrations of most actinides. All methods agree within 11% about the average for all fission products studied. Most deviations are less than 10%, and many are less than 5%. The exceptions are Sm 149, Sm 151, and Gd 155.

  10. Proceedings of the OECD/CSNI workshop on transient thermal-hydraulic and neutronic codes requirements

    SciTech Connect (OSTI)

    Ebert, D.

    1997-07-01

    This is a report on the CSNI Workshop on Transient Thermal-Hydraulic and Neutronic Codes Requirements held at Annapolis, Maryland, USA November 5-8, 1996. This experts` meeting consisted of 140 participants from 21 countries; 65 invited papers were presented. The meeting was divided into five areas: (1) current and prospective plans of thermal hydraulic codes development; (2) current and anticipated uses of thermal-hydraulic codes; (3) advances in modeling of thermal-hydraulic phenomena and associated additional experimental needs; (4) numerical methods in multi-phase flows; and (5) programming language, code architectures and user interfaces. The workshop consensus identified the following important action items to be addressed by the international community in order to maintain and improve the calculational capability: (a) preserve current code expertise and institutional memory, (b) preserve the ability to use the existing investment in plant transient analysis codes, (c) maintain essential experimental capabilities, (d) develop advanced measurement capabilities to support future code validation work, (e) integrate existing analytical capabilities so as to improve performance and reduce operating costs, (f) exploit the proven advances in code architecture, numerics, graphical user interfaces, and modularization in order to improve code performance and scrutibility, and (g) more effectively utilize user experience in modifying and improving the codes.

  11. OECD MCCI project enhancing instrumentation for reactor materials experiments, Rev. 0 September 3, 2002.

    SciTech Connect (OSTI)

    Lomperski, S.; Basu, S.

    2011-05-23

    Reactor safety experiments for studying the reactions of a molten core (corium) with water and/or concrete involve materials at extremely high temperature. Such high temperature severely restricts the types of sensors that can be employed to measure characteristics of the corium itself. Yet there is great interest in improving instrumentation so that the state of the melt can be established with more precision. In particular, it would be beneficial to increase both the upper range limit and accuracy of temperature measurements. The poor durability of thermocouples at high temperature is also an important issue. For experiments involving a water-quenched melt, direct measurements of the growth rate of the crust separating the melt and water would be of great interest. This is a key element in determining the nature of heat transfer between the melt and coolant. Despite its importance, no one has been able to directly measure the crust thickness during such tests. This paper considers three specialized sensors that could be introduced to enhance melt characterization: (1) A commercially fabricated, single point infrared temperature measurement with the footprint of a thermowell. A lens assembly and fiber optic cable linked to a receiver and amplifier measures the temperature at the base of a tungsten thermowell. The upper range limit is 3000 C and accuracy is {+-}0.25% of the reading. (2) In-house development of an ultrasonic temperature sensor that would provide multipoint measurements at temperatures up to {approx}3000 C. The sensors are constructed from tungsten rods and have a high temperature durability that is superior to that of thermocouples. (3) In-house development of an ultrasonic probe to measure the growth rate of the corium crust. This ultrasonic sensor would include a tungsten waveguide that transmits ultrasonic pulses up through the corium melt towards the crust and detects reflections from the melt/crust interface. A measurement of the echo time delay would provide the location of the interface. These three sensors would provide a considerable upgrade of the instrumentation used in our reactor materials tests. The infracouple is a commercial product that could provide an immediate improvement in temperature measurements. The sensor could also serve to corroborate thermocouple data by providing a measurement based upon a different physical principle. The ultrasonic temperature sensor would involve a greater investment and longer time frame than the infracouple, but offers all the advantages of the infracouple along with miniaturization and the ability to measure at multiple locations. In addition, the UTS is the platform from which we would begin development of the crust detector. Of the three sensors, the crust detector requires the most effort and entails the greatest uncertainty. However, a real-time crust thickness measurement has never before been made and such data would be unique and of great benefit to reactor materials experiments.

  12. OECD NEA Benchmark Database of Spent Nuclear Fuel Isotopic Compositions for World Reactor Designs

    SciTech Connect (OSTI)

    Gauld, Ian C; Sly, Nicholas C; Michel-Sendis, Franco

    2014-01-01

    Experimental data on the isotopic concentrations in irradiated nuclear fuel represent one of the primary methods for validating computational methods and nuclear data used for reactor and spent fuel depletion simulations that support nuclear fuel cycle safety and safeguards programs. Measurement data have previously not been available to users in a centralized or searchable format, and the majority of accessible information has been, for the most part, limited to light-water-reactor designs. This paper describes a recent initiative to compile spent fuel benchmark data for additional reactor designs used throughout the world that can be used to validate computer model simulations that support nuclear energy and nuclear safeguards missions. Experimental benchmark data have been expanded to include VVER-440, VVER-1000, RBMK, graphite moderated MAGNOX, gas cooled AGR, and several heavy-water moderated CANDU reactor designs. Additional experimental data for pressurized light water and boiling water reactor fuels has also been compiled for modern assembly designs and more extensive isotopic measurements. These data are being compiled and uploaded to a recently revised structured and searchable database, SFCOMPO, to provide the nuclear analysis community with a centrally-accessible resource of spent fuel compositions that can be used to benchmark computer codes, models, and nuclear data. The current version of SFCOMPO contains data for eight reactor designs, 20 fuel assembly designs, more than 550 spent fuel samples, and measured isotopic data for about 80 nuclides.

  13. Environmental site description for a Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) production plant at the Portsmouth Gaseous Diffusion Plant site

    SciTech Connect (OSTI)

    Marmer, G.J.; Dunn, C.P.; Filley, T.H.; Moeller, K.L.; Pfingston, J.M.; Policastro, A.J.; Cleland, J.H.

    1991-09-01

    Uranium enrichment in the United States has utilized a diffusion process to preferentially enrich the U-235 isotope in the uranium product. In the 1970s, the US Department of Energy (DOE) began investigating more efficient and cost-effective enrichment technologies. In January 1990, the Secretary of Energy approved a plan for the demonstration and deployment of the Uranium Atomic Vapor Laser isotope Separation (U-AVLIS) technology with the near-term goal to provide the necessary information to make a deployment decision by November 1992. Initial facility operation is anticipated for 1999. A programmatic document for use in screening DOE sites to locate a U-AVLIS production plant was developed and implemented in two parts. The first part consisted of a series of screening analyses, based on exclusionary and other criteria, that identified a reasonable number of candidate sites. The final evaluation, which included sensitivity studies, identified the Oak Ridge Gaseous Diffusion Plant (ORGDP) site, the Paducah Gaseous Diffusion Plant (PGDP) site, and the Portsmouth Gaseous Diffusion Plant (PORTS) site as having significant advantages over the other sites considered. This environmental site description (ESD) provides a detailed description of the PORTS site and vicinity suitable for use in an environmental impact statement (EIS). This report is based on existing literature, data collected at the site, and information collected by Argonne National Laboratory (ANL) staff during site visits. The organization of the ESD is as follows. Topics addressed in Sec. 2 include a general site description and the disciplines of geology, water resources, biotic resources, air resources, noise, cultural resources, land use. Socioeconomics, and waste management. Identification of any additional data that would be required for an EIS is presented in Sec. 3.

  14. Revenue Requirements Modeling System (RRMS) documentation. Volume I. Methodology description and user's guide. Appendix A: model abstract; Appendix B: technical appendix; Appendix C: sample input and output. [Compustat

    SciTech Connect (OSTI)

    Not Available

    1986-03-01

    The Revenue Requirements Modeling System (RRMS) is a utility specific financial modeling system used by the Energy Information Administration (EIA) to evaluate the impact on electric utilities of changes in the regulatory, economic, and tax environments. Included in the RRMS is a power plant life-cycle revenue requirements model designed to assess the comparative economic advantage of alternative generating plant. This report is Volume I of a 2-volume set and provides a methodology description and user's guide, a model abstract and technical appendix, and sample input and output for the models. Volume II provides an operator's manual and a program maintenance guide.

  15. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume IX. Reactor and fuel cycle description

    SciTech Connect (OSTI)

    Not Available

    1980-06-01

    The Nonproliferation Alterntive Systems Assessment Program (NASAP) has characterized and assessed various reactor/fuel-cycle systems. Volume IX provides, in summary form, the technical descriptions of the reactor/fuel-cycle systems studied. This includes the status of the system technology, as well as a discussion of the safety, environmental, and licensing needs from a technical perspective. This information was then used in developing the research, development, and demonstration (RD and D) program, including its cost and time frame, to advance the existing technology to the level needed for commercial use. Wherever possible, the cost data are given as ranges to reflect the uncertainties in the estimates.

  16. On-line Chemistry within WRF: Description and Evaluation of a State-of-the-Art Multiscale Air Quality and Weather Prediction Model

    SciTech Connect (OSTI)

    Grell, Georg; Fast, Jerome D.; Gustafson, William I.; Peckham, Steven E.; McKeen, Stuart A.; Salzmann, Marc; Freitas, Saulo

    2010-01-01

    This is a conference proceeding that is now being put together as a book. This is chapter 2 of the book: "INTEGRATED SYSTEMS OF MESO-METEOROLOGICAL AND CHEMICAL TRANSPORT MODELS" published by Springer. The chapter title is "On-line Chemistry within WRF: Description and Evaluation of a State-of-the-Art Multiscale Air Quality and Weather Prediction Model." The original conference was the COST-728/NetFAM workshop on Integrated systems of meso-meteorological and chemical transport models, Danish Meteorological Institute, Copenhagen, May 21-23, 2007.

  17. Study of lubricant circulation in HVAC systems. Volume 1: Description of technical effort and results; Final technical report, March 1995--April 1996

    SciTech Connect (OSTI)

    Biancardi, F.R.; Michels, H.H.; Sienel, T.H.; Pandy, D.R.

    1996-10-01

    The purpose of this program was to conduct experimental and analytical efforts to determine lubricant circulation characteristics of new HFC/POE pairs and HFC/mineral oil pairs in a representative central residential HVAC system and to compare their behavior with the traditional HCFC-22/mineral oil (refrigerant/lubricant) pair. A dynamic test facility was designed and built to conduct the experimental efforts. This facility provided a unique capability to visually and physically measure oil circulation rates, on-line, in operating systems. A unique on-line ultraviolet-based measurement device was used to obtain detailed data on the rate and level of lubricant oil circulated within the operating heat pump system. The experimental and analytical data developed during the program are presented as a function of vapor velocity, refrigerant/lubricant viscosity, system features and equipment. Both visual observations and instrumentation were used to understand ``worst case`` oil circulation situations. This report is presented in two volumes. Volume 1 contains a complete description of the program scope, objective, test results summary, conclusions, description of test facility and recommendations for future effort. Volume 2 contains all of the program test data essentially as taken from the laboratory dynamic test facility during the sequence of runs.

  18. Benchmarking the performance of density functional theory and point charge force fields in their description of sI methane hydrate against diffusion Monte Carlo

    SciTech Connect (OSTI)

    Cox, Stephen J.; Michaelides, Angelos; Department of Chemistry, University College London, 20 Gordon Street, London WC1H 0AJ ; Towler, Michael D.; Theory of Condensed Matter Group, Cavendish Laboratory, University of Cambridge, J.J. Thomson Avenue, Cambridge CB3 0HE ; Alf, Dario; Department of Earth Sciences, University College London Gower Street, London WC1E 6BT

    2014-05-07

    High quality reference data from diffusion Monte Carlo calculations are presented for bulk sI methane hydrate, a complex crystal exhibiting both hydrogen-bond and dispersion dominated interactions. The performance of some commonly used exchange-correlation functionals and all-atom point charge force fields is evaluated. Our results show that none of the exchange-correlation functionals tested are sufficient to describe both the energetics and the structure of methane hydrate accurately, while the point charge force fields perform badly in their description of the cohesive energy but fair well for the dissociation energetics. By comparing to ice I{sub h}, we show that a good prediction of the volume and cohesive energies for the hydrate relies primarily on an accurate description of the hydrogen bonded water framework, but that to correctly predict stability of the hydrate with respect to dissociation to ice I{sub h} and methane gas, accuracy in the water-methane interaction is also required. Our results highlight the difficulty that density functional theory faces in describing both the hydrogen bonded water framework and the dispersion bound methane.

  19. PRINCEPS: A computer-based approach to the structural description and recognition of trends within structural databases, and its application to the Ce-Ni-Si System

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

    Guo, Yiming; Fredrickson, Daniel C.

    2016-04-01

    Intermetallic crystal structures offer an enormous structural diversity, with an endless array of structural motifs whose connection to stability and physical properties are often mysterious. Making sense of the often complex crystal structures that arise here, developing a clear structural description, and identifying connections to other phases can be laborious and require an encyclopedic knowledge of structure types. In this Article, we present PRINCEPS, an algorithm based on a new coordination environment projection scheme that facilitates the structural analysis and comparison of such crystal structures. We demonstrate the potential of this approach by applying it to the complex Ce-Ni-Si ternarymore » system, whose 17 binary and 21 ternary phases would present a daunting challenge to one seeking to understand the system by manual inspection (but has nonetheless been well-described through the heroic efforts of previous researchers). With the help of PRINCEPS, most of the ternary phases in this system can be rationalized as intergrowths of simple structural fragments, and grouped into a handful of structural series (with some outliers). Lastly, these results illustrate how the PRINCEPS approach can be used to organize a vast collection of crystal structures into structurally meaningful families, and guide the description of complex atomic arrangements.« less

  20. Environmental site description for a Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) production plant at the Paducah Gaseous Diffusion Plant site

    SciTech Connect (OSTI)

    Marmer, G.J.; Dunn, C.P.; Moeller, K.L.; Pfingston, J.M.; Policastro, A.J.; Yuen, C.R.; Cleland, J.H.

    1991-09-01

    Uranium enrichment in the United States has utilized a diffusion process to preferentially enrich the U-235 isotope in the uranium product. The U-AVLIS process is based on electrostatic extraction of photoionized U-235 atoms from an atomic vapor stream created by electron-beam vaporization of uranium metal alloy. The U-235 atoms are ionized when precisely tuned laser light -- of appropriate power, spectral, and temporal characteristics -- illuminates the uranium vapor and selectively photoionizes the U-235 isotope. A programmatic document for use in screening DOE site to locate a U-AVLIS production plant was developed and implemented in two parts. The first part consisted of a series of screening analyses, based on exclusionary and other criteria, that identified a reasonable number of candidate sites. These sites were subjected to a more rigorous and detailed comparative analysis for the purpose of developing a short list of reasonable alternative sites for later environmental examination. This environmental site description (ESD) provides a detailed description of the PGDP site and vicinity suitable for use in an environmental impact statement (EIS). The report is based on existing literature, data collected at the site, and information collected by Argonne National Laboratory (ANL) staff during a site visit. 65 refs., 15 tabs.

  1. Idaho National Engineering and Environmental Laboratory, Old Waste Calcining Facility, Scoville vicinity, Butte County, Idaho -- Photographs, written historical and descriptive data. Historical American engineering record

    SciTech Connect (OSTI)

    1997-12-31

    This report describes the history of the Old Waste Calcining Facility. It begins with introductory material on the Idaho National Engineering and Environmental Laboratory, the Materials Testing Reactor fuel cycle, and the Idaho Chemical Processing Plant. The report then describes management of the wastes from the processing plant in the following chapters: Converting liquid to solid wastes; Fluidized bed waste calcining process and the Waste Calcining Facility; Waste calcining campaigns; WCF gets a new source of heat; New Waste Calcining Facility; Last campaign; Deactivation and the RCRA cap; Significance/context of the old WCF. Appendices contain a photo key map for HAER photos, a vicinity map and neighborhood of the WCF, detailed description of the calcining process, and chronology of WCF campaigns.

  2. Process Description and Operating History for the CPP-601/-640/-627 Fuel Reprocessing Complex at the Idaho National Engineering and Environmental Laboratory

    SciTech Connect (OSTI)

    E. P. Wagner

    1999-06-01

    The Fuel Reprocessing Complex (FRC) at the Idaho Nuclear Technology and Engineering Center at the Idaho National Engineering and Environmental Laboratory was used for reprocessing spent nuclear fuel from the early 1950's until 1992. The reprocessing facilities are now scheduled to be deactivated. As part of the deactivation process, three Resource Conservation and Recovery Act (RCRA) interim status units located in the complex must be closed. This document gathers the historical information necessary to provide a rational basis for the preparation of a comprehensive closure plan. Included are descriptions of process operations and the operating history of the FRC. A set of detailed tables record the service history and present status of the process vessels and transfer lines.

  3. Hanford Waste Vitrification Plant Quality Assurance Program description for high-level waste form development and qualification. Revision 3, Part 2

    SciTech Connect (OSTI)

    Not Available

    1993-08-01

    The Hanford Waste Vitrification Plant Project has been established to convert the high-level radioactive waste associated with nuclear defense production at the Hanford Site into a waste form suitable for disposal in a deep geologic repository. The Hanford Waste Vitrification Plant will mix processed radioactive waste with borosilicate material, then heat the mixture to its melting point (vitrification) to forin a glass-like substance that traps the radionuclides in the glass matrix upon cooling. The Hanford Waste Vitrification Plant Quality Assurance Program has been established to support the mission of the Hanford Waste Vitrification Plant. This Quality Assurance Program Description has been written to document the Hanford Waste Vitrification Plant Quality Assurance Program.

  4. Kinetic description of intense nonneutral beam propagation through a periodic solenoidal focusing field based on the nonlinear Vlasov-Maxwell equations

    SciTech Connect (OSTI)

    Davidson, R.C.; Chen, C.

    1997-08-01

    A kinetic description of intense nonneutral beam propagation through a periodic solenoidal focusing field B{sup sol}({rvec x}) is developed. The analysis is carried out for a thin beam with characteristic beam radius r{sub b} {much_lt} S, and directed axial momentum {gamma}{sub b}m{beta}{sub b}c (in the z-direction) large compared with the transverse momentum and axial momentum spread of the beam particles. Making use of the nonlinear Vlasov-Maxwell equations for general distribution function f{sub b}({rvec x},{rvec p},t) and self-consistent electrostatic field consistent with the thin-beam approximation, the kinetic model is used to investigate detailed beam equilibrium properties for a variety of distribution functions. Examples are presented both for the case of a uniform solenoidal focusing field B{sub z}(z) = B{sub 0} = const. and for the case of a periodic solenoidal focusing field B{sub z}(z + S) = B{sub z}(z). The nonlinear Vlasov-Maxwell equations are simplified in the thin-beam approximation, and an alternative Hamiltonian formulation is developed that is particularly well-suited to intense beam propagation in periodic focusing systems. Based on the present analysis, the Vlasov-Maxwell description of intense nonneutral beam propagation through a periodic solenoidal focusing field {rvec B}{sup sol}({rvec x}) is found to be remarkably tractable and rich in physics content. The Vlasov-Maxwell formalism developed here can be extended in a straightforward manner to investigate detailed stability behavior for perturbations about specific choices of beam equilibria.

  5. A preliminary regional PBPK model of lung metabolism for improving species dependent descriptions of 1,3-butadiene and its metabolites

    SciTech Connect (OSTI)

    Campbell, Jerry; Van Landingham, Cynthia; Crowell, Susan; Gentry, Robinan; Kaden, Debra; Fiebelkorn, Stacy; Loccisano, Anne; Clewell, Harvey

    2015-06-12

    1,3-Butadiene (BD), a volatile organic chemical (VOC), is used in synthetic rubber production and other industrial processes. It is detectable at low levels in ambient air as well as in tobacco smoke and gasoline vapors. Inhalation exposures to high concentrations of BD have been associated with lung cancer in both humans and experimental animals, although differences in species sensitivity have been observed. Metabolically active lung cells such as Pulmonary Type I and Type II epithelial cells and club cells (Clara cells)1 are potential targets of BD metabolite-induced toxicity. Metabolic capacities of these cells, their regional densities, and distributions vary throughout the respiratory tract as well as between species and cell types. Here we present a physiologically based pharmacokinetic (PBPK) model for BD that includes a regional model of lung metabolism, based on a previous model for styrene, to provide species-dependent descriptions of BD metabolism in the mouse, rat, and human. Since there are no in vivo data on BD pharmacokinetics in the human, the rat and mouse models were parameterized to the extent possible on the basis of in vitro metabolic data. Where it was necessary to use in vivo data, extrapolation from rat to mouse was performed to evaluate the level of uncertainty in the human model. A kidney compartment and description of downstream metabolism were also included in the model to allow for eventual use of available urinary and blood biomarker data in animals and humans to calibrate the model for estimation of BD exposures and internal metabolite levels. Results from simulated inhalation exposures to BD indicate that incorporation of differential lung region metabolism is important in describing species differences in pulmonary response and that these differences may have implications for risk assessments of human exposures to BD.

  6. A preliminary regional PBPK model of lung metabolism for improving species dependent descriptions of 1,3-butadiene and its metabolites

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

    Campbell, Jerry; Van Landingham, Cynthia; Crowell, Susan; Gentry, Robinan; Kaden, Debra; Fiebelkorn, Stacy; Loccisano, Anne; Clewell, Harvey

    2015-06-12

    1,3-Butadiene (BD), a volatile organic chemical (VOC), is used in synthetic rubber production and other industrial processes. It is detectable at low levels in ambient air as well as in tobacco smoke and gasoline vapors. Inhalation exposures to high concentrations of BD have been associated with lung cancer in both humans and experimental animals, although differences in species sensitivity have been observed. Metabolically active lung cells such as Pulmonary Type I and Type II epithelial cells and club cells (Clara cells)1 are potential targets of BD metabolite-induced toxicity. Metabolic capacities of these cells, their regional densities, and distributions vary throughoutmore » the respiratory tract as well as between species and cell types. Here we present a physiologically based pharmacokinetic (PBPK) model for BD that includes a regional model of lung metabolism, based on a previous model for styrene, to provide species-dependent descriptions of BD metabolism in the mouse, rat, and human. Since there are no in vivo data on BD pharmacokinetics in the human, the rat and mouse models were parameterized to the extent possible on the basis of in vitro metabolic data. Where it was necessary to use in vivo data, extrapolation from rat to mouse was performed to evaluate the level of uncertainty in the human model. A kidney compartment and description of downstream metabolism were also included in the model to allow for eventual use of available urinary and blood biomarker data in animals and humans to calibrate the model for estimation of BD exposures and internal metabolite levels. Results from simulated inhalation exposures to BD indicate that incorporation of differential lung region metabolism is important in describing species differences in pulmonary response and that these differences may have implications for risk assessments of human exposures to BD.« less

  7. Estimated Cost Description Determination Date:

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

    and installation of x-ray transport, optics, and diagnostics in ESA. It also includes the construction of an annex to End Station A , providing hutches for experiment stations. ...

  8. PURPOSE FORM INSTRUCTIONS Item Description

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

    types can be found on the "Contract Types" worksheet in the NETL Subcontractor Report Excel workbook. 21 Enter "Competitive" or "Non-Competitive" depending on the method used...

  9. HEB spool pieces design description

    SciTech Connect (OSTI)

    Clark, D.; Strube, D.

    1994-02-01

    The many varied types of spool pieces for the High Energy Booster (HEB) of the Superconducting Super Collider (SSC) Laboratory are presented. Each type of spool piece is discussed, and the specific components are identified. The spool piece components allow each spool piece to perform as a unique electromechanical device positioned in series with large superconducting magnets to provide electrical and mechanical support for each superconducting magnet in areas of cryogenics, electrical power, instrumentation, diagnostics, and vacuum. A specialized HEB superspool is identified that perhaps has the potential to aid in the overall configuration management of the HEB lattice by combining HEB superconducting quadrupole magnets and spool pieces within a common cryostat.

  10. Original Workshop Proposal and Description

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

    ... Daniel Rokhsar, LBNL (Bioinformatics) ??? (environmental mod1eling ???) ??? (nano science) ??? (chemistry) ??? (computational neuroscience) Potential DoE and university- and ...

  11. ASSEMBLY TRANSFER SYSTEM DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    B. Gorpani

    2000-06-26

    The Assembly Transfer System (ATS) receives, cools, and opens rail and truck transportation casks from the Carrier/Cask Handling System (CCHS). The system unloads transportation casks consisting of bare Spent Nuclear Fuel (SNF) assemblies, single element canisters, and Dual Purpose Canisters (DPCs). For casks containing DPCs, the system opens the DPCs and unloads the SNF. The system stages the assemblies, transfer assemblies to and from fuel-blending inventory pools, loads them into Disposal Containers (DCs), temporarily seals and inerts the DC, decontaminates the DC and transfers it to the Disposal Container Handling System. The system also prepares empty casks and DPCs for off-site shipment. Two identical Assembly Transfer System lines are provided in the Waste Handling Building (WHB). Each line operates independently to handle the waste transfer throughput and to support maintenance operations. Each system line primarily consists of wet and dry handling areas. The wet handling area includes a cask transport system, cask and DPC preparation system, and a wet assembly handling system. The basket transport system forms the transition between the wet and dry handling areas. The dry handling area includes the dry assembly handling system, assembly drying system, DC preparation system, and DC transport system. Both the wet and dry handling areas are controlled by the control and tracking system. The system operating sequence begins with moving transportation casks to the cask preparation area. The cask preparation operations consist of cask cavity gas sampling, cask venting, cask cool-down, outer lid removal, and inner shield plug lifting fixture attachment. Casks containing bare SNF (no DPC) are filled with water and placed in the cask unloading pool. The inner shield plugs are removed underwater. For casks containing a DPC, the cask lid(s) is removed, and the DPC is penetrated, sampled, vented, and cooled. A DPC lifting fixture is attached and the cask is placed into the cask unloading pool. In the cask unloading pool the DPC is removed from the cask and placed in an overpack and the DPC lid is severed and removed. Assemblies are removed from either an open cask or DPC and loaded into assembly baskets positioned in the basket staging rack in the assembly unloading pool. A method called ''blending'' is utilized to load DCs with a heat output of less than 11.8 kW. This involves combining hotter and cooler assemblies from different baskets. Blending requires storing some of the hotter fuel assemblies in fuel-blending inventory pools until cooler assemblies are available. The assembly baskets are then transferred from the basket staging rack to the assembly handling cell and loaded into the assembly drying vessels. After drying, the assemblies are removed from the assembly drying vessels and loaded into a DC positioned below the DC load port. After installation of a DC inner lid and temporary sealing device, the DC is transferred to the DC decontamination cell where the top area of the DC, the DC lifting collar, and the DC inner lid and temporary sealing device are decontaminated, and the DC is evacuated and backfilled with inert gas to prevent prolonged clad exposure to air. The DC is then transferred to the Disposal Container Handling System for lid welding. In another cask preparation and decontamination area, lids are replaced on the empty transportation casks and DPC overpacks, the casks and DPC overpacks are decontaminated, inspected, and transferred to the Carrier/Cask Handling System for shipment off-site. All system equipment is designed to facilitate manual or remote operation, decontamination, and maintenance. The system interfaces with the Carrier/Cask Handling System for incoming and outgoing transportation casks and DPCs. The system also interfaces with the Disposal Container Handling System, which prepares the DC for loading and subsequently seals the loaded DC. The system support interfaces are the Waste Handling Building System and other internal WHB support systems.

  12. CANISTER TRANSFER SYSTEM DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    B. Gorpani

    2000-06-23

    The Canister Transfer System receives transportation casks containing large and small disposable canisters, unloads the canisters from the casks, stores the canisters as required, loads them into disposal containers (DCs), and prepares the empty casks for re-shipment. Cask unloading begins with cask inspection, sampling, and lid bolt removal operations. The cask lids are removed and the canisters are unloaded. Small canisters are loaded directly into a DC, or are stored until enough canisters are available to fill a DC. Large canisters are loaded directly into a DC. Transportation casks and related components are decontaminated as required, and empty casks are prepared for re-shipment. One independent, remotely operated canister transfer line is provided in the Waste Handling Building System. The canister transfer line consists of a Cask Transport System, Cask Preparation System, Canister Handling System, Disposal Container Transport System, an off-normal canister handling cell with a transfer tunnel connecting the two cells, and Control and Tracking System. The Canister Transfer System operating sequence begins with moving transportation casks to the cask preparation area with the Cask Transport System. The Cask Preparation System prepares the cask for unloading and consists of cask preparation manipulator, cask inspection and sampling equipment, and decontamination equipment. The Canister Handling System unloads the canister(s) and places them into a DC. Handling equipment consists of a bridge crane hoist, DC loading manipulator, lifting fixtures, and small canister staging racks. Once the cask has been unloaded, the Cask Preparation System decontaminates the cask exterior and returns it to the Carrier/Cask Handling System via the Cask Transport System. After the DC is fully loaded, the Disposal Container Transport System moves the DC to the Disposal Container Handling System for welding. To handle off-normal canisters, a separate off-normal canister handling cell is located adjacent to the canister transfer cell and is interconnected to the transfer cell by means of the off-normal canister transfer tunnel. All canister transfer operations are controlled by the Control and Tracking System. The system interfaces with the Carrier/Cask Handling System for incoming and outgoing transportation casks. The system also interfaces with the Disposal Container Handling System, which prepares the DC for loading and subsequently seals the loaded DC. The system support interfaces are the Waste Handling Building System and other internal Waste Handling Building (WHB) support systems.

  13. WIPP WASTE MINIMIZATION PROGRAM DESCRIPTION

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

    NOV 2 3 2015 New Mexico Environment Department 2905 Rodeo Park Drive East, Building 1 Santa Fe, New Mexico 87505-6303 Subject: Transm ittal of the Waste Isolation Pilot Plant Project 2015 Waste Minimization Report, Permit Number NM4890139088-TSDF Dear Mr. Kieling: The purpose of this letter is to provide you with the Waste Isolation Pilot Plant (WIPP) Project 2015 Waste Minimization Report. This report, required by and prepared in accordance with the WIPP Hazardous Waste Facility Permit Part 2,

  14. WIPP WASTE MINIMIZATION PROGRAM DESCRIPTION

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

    Carlsbad, New Mexico 8822 1 NOV 2 3 2011 Mr. John Kieling , Acting Bureau Chief Hazardous Waste Bureau New Mexico Environme nt Department 2905 Rodeo Park Drive East, Building 1 Santa Fe, New Mexico 87505-6303 Subject: Transmittal of the Waste Isolation Pilot Plant Annual Waste Minimization Report Dear Mr. Kieling: This letter provides the submittal of the Waste Isolation Pilot Plant Annual Waste Minimization Report. This report is required by and has bee n prepared in accordance with the WIPP

  15. Visiting Faculty Program Program Description

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

    covers stipend and travel reimbursement for the 10-week program. Teacherfaculty participants: 1 Program Coordinator: Scott Robbins Email: srobbins@lanl.gov Phone number: 663-5621...

  16. Student Internship Programs Program Description

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

    for a summer high school student to 75,000 for a Ph.D. student working full-time for a year. Program Coordinator: Scott Robbins Email: srobbins@lanl.gov Phone number: 663-5621...

  17. WIPP WASTE MINIMIZATION PROGRAM DESCRIPTION

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

    ... NMSW - New Mexico Special Waste MSW - Municipal Solid Waste C&D - Construction and ... Proposed waste streams that could generate hazardous wastes are reviewed regularly to ...

  18. WIPP WASTE MINIMIZATION PROGRAM DESCRIPTION

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

    New Mexico 8822 1 NOV 2 3 2011 Mr. John Kieling , Acting Bureau Chief Hazardous Waste Bureau New Mexico Environme nt Department 2905 Rodeo Park Drive East, Building 1 Santa...

  19. Description of CBECS Building Types

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

    or public safety. jail, reformatory, or penitentiary courthouse or probation office fire or police station Top Religious Worship Buildings in which people gather for religious...

  20. Description of CBECS Building Types

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

    Buildings used for the preservation of law and order or public safety. police station fire station jail, reformatory, or penitentiary courthouse or probation office Top Religious...

  1. Notices Description: Entergy Services, Inc.

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

    ... responsibilities in an environmentally sound, timely, and fiscally prudent manner. ... indicating that minor to moderate damage could typically be expected from an earthquake. ...

  2. Nuclear Industry Job Descriptions Boilermaker

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

    and addressing and resolving chemistry operating problems. ... D&D Engineer Specializing in planning and execution of ... Emergency Management Specialist Responsible for developing ...

  3. Quality Assurance Requirements and Description

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

    Our mission is to manage and dispose ofbigh-Ievel radioactive waste and spent nuclear fuel in a ... wheels, electrical cabinets, control panels, loudspeakers, etc. where special ...

  4. High Exposure Facility Technical Description

    SciTech Connect (OSTI)

    Carter, Gregory L.; Stithem, Arthur R.; Murphy, Mark K.; Smith, Alex K.

    2008-02-12

    The High Exposure Facility is a collimated high-level gamma irradiator that is located in the basement of the 318 building. It was custom developed by PNNL back in 1982 to meet the needs for high range radiological instrument calibrations and dosimeter irradiations. At the time no commercially available product existed that could create exposure rates up to 20,000 R/h. This document is intended to pass on the design criteria that was employed to create this unique facility, while maintaining compliance with ANSI N543-1974, "General Safety Standard for Installations Using Non-Medical X-Ray and Sealed Gamma-Ray Sources, Energies up to 10 MeV."

  5. Section I - FUNDING OPPORTUNITY DESCRIPTION

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

    ... For early stage transformational technologies with the potential for broad transformational impact, the R&D project must carry the technology development to the point where others ...

  6. Thermal energy storage program description

    SciTech Connect (OSTI)

    Reimers, E.

    1989-03-01

    The U.S. Department of Energy (DOE) has sponsored applied research, development, and demonstration of technologies aimed at reducing energy consumption and encouraging replacement of premium fuels (notably oil) with renewable or abundant indigenous fuels. One of the technologies identified as being able to contribute to these goals is thermal energy storage (TES). Based on the potential for TES to contribute to the historic mission of the DOE and to address emerging energy issues related to the environment, a program to develop specific TES technologies for diurnal, industrial, and seasonal applications is underway. Currently, the program is directed toward three major application targets: (1) TES development for efficient off-peak building heating and cooling, (2) development of advanced TES building materials, and (3) TES development to reduce industrial energy consumption.

  7. Content of System Design Descriptions

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

    ... For example, a backup diesel generator may have an automatic trip on overspeed or overcurrent. ... each system. 2. FACILITY REMAINING LIFETIME The useful life of the completed SDD ...

  8. Subsurface Facility System Description Document

    SciTech Connect (OSTI)

    Eric Loros

    2001-07-31

    The Subsurface Facility System encompasses the location, arrangement, size, and spacing of the underground openings. This subsurface system includes accesses, alcoves, and drifts. This system provides access to the underground, provides for the emplacement of waste packages, provides openings to allow safe and secure work conditions, and interfaces with the natural barrier. This system includes what is now the Exploratory Studies Facility. The Subsurface Facility System physical location and general arrangement help support the long-term waste isolation objectives of the repository. The Subsurface Facility System locates the repository openings away from main traces of major faults, away from exposure to erosion, above the probable maximum flood elevation, and above the water table. The general arrangement, size, and spacing of the emplacement drifts support disposal of the entire inventory of waste packages based on the emplacement strategy. The Subsurface Facility System provides access ramps to safely facilitate development and emplacement operations. The Subsurface Facility System supports the development and emplacement operations by providing subsurface space for such systems as ventilation, utilities, safety, monitoring, and transportation.

  9. System Description for the K-25/K-27 D&D Project Polyurethane Foam Delivery System, East Tennessee Technology Park, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    Boris, G.

    2008-02-21

    The Foam Delivery System used in the decontamination and decommissioning (D&D) project for the K-25/K-27 Buildings at the East Tennessee Technology Park (ETTP) is comprised of a trailer-mounted Gusmer{reg_sign} H20/35 Pro-TEC Proportioning Unit and the associated equipment to convey electrical power, air, and foam component material to the unit. This high-pressure, plural-component polyurethane foam pouring system will be used to fill process gas and non-process equipment/piping (PGE/P) within the K-25/K-27 Buildings with polyurethane foam to immobilize contaminants prior to removal. The system creates foam by mixing isocyanate and polyol resin (Resin) component materials. Currently, the project plans to utilize up to six foaming units simultaneously during peak foaming activities. Also included in this system description are the foam component material storage containers that will be used for storage of the component material drums in a staging area outside of the K-25/K-27 Buildings. The Foam Delivery System and foam component material storage enclosures (i.e., Foaming Component Protective Enclosures) used to store polymeric methylene diphenyl diisocyanate (PMDI) component material are identified as Safety Significant (SS) Structures, Systems and Components (SSC) in the Documented Safety Analysis (DSA) for the project, Documented Safety Analysis for the K-25 and K-27 Facilities at the East Tennessee Technology Park, Oak Ridge, Tennessee, DSA-ET-K-25/K-27-0001.

  10. High-quality permanent draft genome sequence of the extremely osmotolerant diphenol degrading bacterium Halotalea alkalilenta AW-7T, and emended description of the genus Halotalea

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

    Ntougias, Spyridon; Lapidus, Alla; Copeland, Alex; Reddy, T. B. K.; Pati, Amrita; Ivanova, Natalia N.; Markowitz, Victor M.; Klenk, Hans-Peter; Woyke, Tanja; Fasseas, Constantinos; et al

    2015-08-13

    Members of the genus Halotalea (family Halomonadaceae) are of high significance since they can tolerate the greatest glucose and maltose concentrations ever reported for known bacteria and are involved in the degradation of industrial effluents. Here, the characteristics and the permanent-draft genome sequence and annotation of Halotalea alkalilenta AW-7T are described. The microorganism was sequenced as a part of the Genomic Encyclopedia of Type Strains, Phase I: the one thousand microbial genomes (KMG) project at the DOE Joint Genome Institute, and it is the only strain within the genus Halotalea having its genome sequenced. The genome is 4,467,826 bp longmore » and consists of 40 scaffolds with 64.62 % average GC content. A total of 4,104 genes were predicted, comprising of 4,028 protein-coding and 76 RNA genes. Most protein-coding genes (87.79 %) were assigned to a putative function. Halotalea alkalilenta AW-7T encodes the catechol and protocatechuate degradation to β-ketoadipate via the β-ketoadipate and protocatechuate ortho-cleavage degradation pathway, and it possesses the genetic ability to detoxify fluoroacetate, cyanate and acrylonitrile. Lastly, an emended description of the genus Halotalea Ntougias et al. 2007 is also provided in order to describe the delayed fermentation ability of the type strain.« less

  11. High-quality permanent draft genome sequence of the extremely osmotolerant diphenol degrading bacterium Halotalea alkalilenta AW-7T, and emended description of the genus Halotalea

    SciTech Connect (OSTI)

    Ntougias, Spyridon; Lapidus, Alla; Copeland, Alex; Reddy, T. B. K.; Pati, Amrita; Ivanova, Natalia N.; Markowitz, Victor M.; Klenk, Hans-Peter; Woyke, Tanja; Fasseas, Constantinos; Kyrpides, Nikos C.; Zervakis, Georgios I.

    2015-08-13

    Members of the genus Halotalea (family Halomonadaceae) are of high significance since they can tolerate the greatest glucose and maltose concentrations ever reported for known bacteria and are involved in the degradation of industrial effluents. Here, the characteristics and the permanent-draft genome sequence and annotation of Halotalea alkalilenta AW-7T are described. The microorganism was sequenced as a part of the Genomic Encyclopedia of Type Strains, Phase I: the one thousand microbial genomes (KMG) project at the DOE Joint Genome Institute, and it is the only strain within the genus Halotalea having its genome sequenced. The genome is 4,467,826 bp long and consists of 40 scaffolds with 64.62 % average GC content. A total of 4,104 genes were predicted, comprising of 4,028 protein-coding and 76 RNA genes. Most protein-coding genes (87.79 %) were assigned to a putative function. Halotalea alkalilenta AW-7T encodes the catechol and protocatechuate degradation to β-ketoadipate via the β-ketoadipate and protocatechuate ortho-cleavage degradation pathway, and it possesses the genetic ability to detoxify fluoroacetate, cyanate and acrylonitrile. Lastly, an emended description of the genus Halotalea Ntougias et al. 2007 is also provided in order to describe the delayed fermentation ability of the type strain.

  12. YALINA facility a sub-critical Accelerator- Driven System (ADS) for nuclear energy research facility description and an overview of the research program (1997-2008).

    SciTech Connect (OSTI)

    Gohar, Y.; Smith, D. L.; Nuclear Engineering Division

    2010-04-28

    The YALINA facility is a zero-power, sub-critical assembly driven by a conventional neutron generator. It was conceived, constructed, and put into operation at the Radiation Physics and Chemistry Problems Institute of the National Academy of Sciences of Belarus located in Minsk-Sosny, Belarus. This facility was conceived for the purpose of investigating the static and dynamic neutronics properties of accelerator driven sub-critical systems, and to serve as a neutron source for investigating the properties of nuclear reactions, in particular transmutation reactions involving minor-actinide nuclei. This report provides a detailed description of this facility and documents the progress of research carried out there during a period of approximately a decade since the facility was conceived and built until the end of 2008. During its history of development and operation to date (1997-2008), the YALINA facility has hosted several foreign groups that worked with the resident staff as collaborators. The participation of Argonne National Laboratory in the YALINA research programs commenced in 2005. For obvious reasons, special emphasis is placed in this report on the work at YALINA facility that has involved Argonne's participation. Attention is given here to the experimental program at YALINA facility as well as to analytical investigations aimed at validating codes and computational procedures and at providing a better understanding of the physics and operational behavior of the YALINA facility in particular, and ADS systems in general, during the period 1997-2008.

  13. Photochemistry of the water dimer: Time-dependent quantum wave-packet description of the dynamics at the S{sub 1}-S{sub 0} conical intersection

    SciTech Connect (OSTI)

    Chmura, Bartosz; Rode, Michal F.; Sobolewski, Andrzej L.; Lan Zhenggang

    2009-10-07

    The photoinduced electron-driven proton-transfer dynamics of the water-dimer system has been investigated by time-dependent quantum wave-packet calculations. The main nuclear degrees of freedom driving the system from the Frank-Condon region to the S{sub 0}-S{sub 1} conical intersection are the distance between the oxygen atoms and the displacement of the hydrogen atom from the oxygen-oxygen bond center. Two important coupling modes have been investigated: Rotation of the H-donating water dangling proton and asymmetric stretching of the H-accepting water dangling protons'O{sub a}H bonds. Potential energy surfaces of the ground and lowest excited electronic states have been constructed on the basis of ab initio calculations. The time-dependent quantum wave-packet propagation has been employed within the (2 + 1)-dimensional systems for the description of the nonadiabatic dynamics of water dimer. The effects of the initial vibrational state of the system on the electronic population transfer and dissociation dynamics are presented. To approximate the photochemical behavior of water dimer in bulk water, we add a boundary condition into the (2 + 1)-dimensional systems to simulate the existence of water bulk. The results provide insight into the mechanisms of excited state deactivation of the water-dimer system in gas phase and in bulk water through the electron-driven proton-transfer process.

  14. Gulf Coast geopressured-geothermal program summary report compilation. Volume 2-A: Resource description, program history, wells tested, university and company based research, site restoration

    SciTech Connect (OSTI)

    John, C.J.; Maciasz, G.; Harder, B.J.

    1998-06-01

    The US Department of Energy established a geopressured-geothermal energy program in the mid 1970`s as one response to America`s need to develop alternate energy resources in view of the increasing dependence on imported fossil fuel energy. This program continued for 17 years and approximately two hundred million dollars were expended for various types of research and well testing to thoroughly investigate this alternative energy source. This volume describes the following studies: Geopressured-geothermal resource description; Resource origin and sediment type; Gulf Coast resource extent; Resource estimates; Project history; Authorizing legislation; Program objectives; Perceived constraints; Program activities and structure; Well testing; Program management; Program cost summary; Funding history; Resource characterization; Wells of opportunity; Edna Delcambre No. 1 well; Edna Delcambre well recompletion; Fairfax Foster Sutter No. 2 well; Beulah Simon No. 2 well; P.E. Girouard No. 1 well; Prairie Canal No. 1 well; Crown Zellerbach No. 2 well; Alice C. Plantation No. 2 well; Tenneco Fee N No. 1 well; Pauline Kraft No. 1 well; Saldana well No. 2; G.M. Koelemay well No. 1; Willis Hulin No. 1 well; Investigations of other wells of opportunity; Clovis A. Kennedy No. 1 well; Watkins-Miller No. 1 well; Lucien J. Richard et al No. 1 well; and the C and K-Frank A. Godchaux, III, well No. 1.

  15. Two-fermion-four-boson description of {sup 198}Hg within the U{sub {nu}}(6/12) x U{sub {pi}}(6/4) extended nuclear structure supersymmetry

    SciTech Connect (OSTI)

    Bernards, C.; Heinze, S.; Jolie, J.; Fransen, C.; Linnemann, A.; Radeck, D.

    2009-05-15

    Using the U{sub {nu}}(6/12) x U{sub {pi}}(6/4) extended supersymmetry, we constructed the energy spectrum and electromagnetic transition properties of the supermultiplet member {sup 198}Hg with two proton fermions coupled to a neutron boson core. Consistency between the supersymmetric interacting boson fermion fermion approximation (IBFFA) description and the F-spin symmetric interacting boson approximation (IBA-2) description is shown for this two-fermion-N-boson multiplet member. The data of a {gamma}{gamma} angular correlation experiment using the HORUS cube {gamma}-ray spectrometer--determining new multipole mixing ratios, level spins, {gamma} transitions, and energy states--shows quite a good agreement, also for the low-energy part of the spectrum, when comparing theoretical predictions and experimental data. This is contrary to the usual assumption that a two-fermion-N-boson constellation should describe just the excited two-quasiparticle states.

  16. OECD MCCI project long-term 2-D molten core concrete interaction test design report, Rev. 0. September 30, 2002.

    SciTech Connect (OSTI)

    Farmer, M. T.; Kilsdonk, D. J.; Lomperski, S.; Aeschliman, R. W.; Basu, S. (Nuclear Engineering Division); (NRC)

    2011-05-23

    The Melt Attack and Coolability Experiments (MACE) program at Argonne National Laboratory addressed the issue of the ability of water to cool and thermally stabilize a molten core-concrete interaction when the reactants are flooded from above. These tests provided data regarding the nature of corium interactions with concrete, the heat transfer rates from the melt to the overlying water pool, and the role of noncondensable gases in the mixing processes that contribute to melt quenching. As a follow-on program to MACE, The Melt Coolability and Concrete Interaction Experiments (MCCI) project is conducting reactor material experiments and associated analysis to achieve the following two technical objectives: (1) resolve the ex-vessel debris coolability issue through a program that focuses on providing both confirmatory evidence and test data for the coolability mechanisms identified in MACE integral effects tests, and (2) address remaining uncertainties related to long-term two-dimensional molten core-concrete interactions under both wet and dry cavity conditions. Achievement of these two objectives will demonstrate the efficacy of severe accident management guidelines for existing plants, and provide the technical basis for better containment designs for future plants. In terms of the first program objective, the Small-Scale Water Ingression and Crust Strength (SSWICS) test series has been initiated to provide fundamental information on the ability of water to ingress into cracks and fissures that form in the debris during quench, thereby augmenting the otherwise conduction-limited heat transfer process. A test plan for Melt Eruption Separate Effects Tests (MESET) has also been developed to provide information on the extent of crust growth and melt eruptions as a function of gas sparging rate under well-controlled experiment conditions. In terms of the second program objective, the project Management Board (MB) has approved startup activities required to carry out experiments to address remaining uncertainties related to long-term two-dimensional molten core-concrete interaction. In particular, for both wet and dry cavity conditions, there is uncertainty insofar as evaluating the lateral vs. axial power split during a core-concrete interaction due to a lack of experiment data. As a result, there are differences in the 2-D cavity erosion predicted by codes such as MELCOR, WECHSL, and COSACO. The first step towards generating this data is to produce a test plan for review by the Project Review Group (PRG). The purpose of this document is to provide this plan.

  17. Consistent Comparison of the Codes RELAP5/PARCS and TRAC-M/PARCS for the OECD MSLB Coupled Code Benchmark

    SciTech Connect (OSTI)

    Kozlowski, Tomasz; Miller, R. Matthew; Downar, Thomas J.; Barber, Douglas A.; Joo, Han Gyu

    2004-04-15

    A generalized interface module was developed for coupling any thermal-hydraulic code to any spatial kinetic code. In the design used here the thermal-hydraulic and spatial kinetic codes function as independent processes and communicate using the Parallel Virtual Machine software. This approach helps maximize flexibility while minimizing modifications to the respective codes. Using this interface, the U.S. Nuclear Regulatory Commission (NRC) three-dimensional neutron kinetic code, Purdue Advanced Reactor Core Simulator (PARCS), has been coupled to the NRC system analysis codes RELAP5 and Modernized Transient Reactor Analysis Code (TRAC-M). Consistent comparison of code results for the Organization for Economic Cooperation and Development/Nuclear Energy Agency main steam line break benchmark problem using RELAP5/PARCS and TRAC-M/PARCS was made to assess code performance.

  18. Simulation of the OECD Main-Steam-Line-Break Benchmark Exercise 3 Using the Coupled RELAP5/PANTHER Codes

    SciTech Connect (OSTI)

    Schneidesch, Christophe R.; Zhang Jinzhao

    2004-04-15

    The RELAP5 best-estimate thermal-hydraulic system code has been coupled with the PANTHER three-dimensional neutron kinetics code via the TALINK dynamic data exchange control and processing tool. The coupled RELAP5/PANTHER code package has been qualified and will be used at Tractebel Engineering (TE) for analyzing asymmetric pressurized water reactor (PWR) accidents with strong core-system interactions. The Organization for Economic Cooperation and Development/U.S. Nuclear Regulatory Commission PWR main-steam-line-break benchmark problem was analyzed as part of the qualification efforts to demonstrate the capability of the coupled code package of simulating such transients. This paper reports the main results of TE's contribution to the benchmark Exercise 3.

  19. Optimal Conventional and Semi-Natural Treatments for the Upper Yakima Spring Chinook Salmon Supplementation Project; Treatment Definitions and Descriptions and Biological Specifications for Facility Design, 1995-1999 Final Report.

    SciTech Connect (OSTI)

    Hager, Robert C.; Costello, Ronald J.

    1999-10-01

    This report describes the Yakima Fisheries Project facilities (Cle Elum Hatchery and acclimation satellites) which provide the mechanism to conduct state-of-the-art research for addressing questions about spring chinook supplementation strategies. The definition, descriptions, and specifications for the Yakima spring chinook supplementation program permit evaluation of alternative fish culture techniques that should yield improved methods and procedures to produce wild-like fish with higher survival that can be used to rebuild depleted spring chinook stocks of the Columbia River Basin. The definition and description of three experimental treatments, Optimal Conventional (OCT), Semi-Natural (SNT), Limited Semi-Natural (LSNT), and the biological specifications for facilities have been completed for the upper Yakima spring chinook salmon stock of the Yakima Fisheries Project. The task was performed by the Biological Specifications Work Group (BSWG) represented by Yakama Indian Nation, Washington Department of Fish and Wildlife, National Marine Fisheries Service, and Bonneville Power Administration. The control and experimental variables of the experimental treatments (OCT, SNT, and LSNT) are described in sufficient detail to assure that the fish culture facilities will be designed and operated as a production scale laboratory to produce and test supplemented upper Yakima spring chinook salmon. Product specifications of the treatment groups are proposed to serve as the generic templates for developing greater specificity for measurements of product attributes. These product specifications will be used to monitor and evaluate treatment effects, with respect to the biological response variables (post release survival, long-term fitness, reproductive success and ecological interactions).

  20. Property description and fact-finding report for NPR-3 Natrona County, Wyoming. Addendum to 22 August 1996 study of alternatives for future operations of the naval petroleum and oil shale reserves NPR-3

    SciTech Connect (OSTI)

    1997-05-01

    The U.S. Department of Energy has asked Gustavson Associates, Inc. to serve as an Independent Petroleum Consultant under contract DE-AC01-96FE64202. This authorizes a study and recommendations regarding future development of Naval Petroleum Reserve No. 3 (NPR-3) in Natrona County, Wyoming. The report that follows is the Phase I fact-finding and property description for that study. The United States of America owns 100 percent of the mineral rights and surface rights in 9,321-acre NPR-3. This property comprises the Teapot Dome oil field and related production, processing and other facilities. Discovered in 1914, this field has 632 wells producing 1,807 barrels of oil per day. Production revenues are about $9.5 million per year. Remaining recoverable reserves are approximately 1.3 million barrels of oil. Significant plugging and abandonment (P&A) and environmental liabilities are present.

  1. 1Headquarters Facilities Master SecurityPlan Section 10 Operations Security Program DescriptionThe goal of Operations Security (OPSEC) is to control information about the capabilities and intentions of an organization in order to keep them from being exp

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

    Revision History: Date Description 6/3/15 Pg. 7-1, Line 6, added text Pg. 701-1, Line 8, added text Pg. 701-1, Line 10, removed last sentence Pg. 701-1, Line 31, removed #5 Pg. 701-1, Line 38, changed date Pg. 701-2, Line 3, added/deleted text Pg. 701-2, Line 9, reworded first sentence Pg. 701-2, Line 19, added text Pg. 701-3, Line 3, added text Pg. 701-3, Line 18, removed last two bullets Pg. 701-4, Line 12, reworded all three bullets Pg. 702-1, Line 13, added new sentence Pg. 702-1, Line 27,

  2. Acquisition Description/ Category Solicitation Method Contract...

    Energy Savers [EERE]

    ... Plus Award Fee 82911-82817 121.1M Moab Remedial Action Contract (Uranium Mill ... Cost Plus Award Fee wFixed Unit Price Component 110411-093016 121M Moab Technical ...

  3. Section C: Description, Specifications and Work Statements

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

    ... NREL's credentials are beyond reproach and NREL is viewed as a definitive resource on energy technology, policy, and market matters. NREL's energy technology, policy, and market ...

  4. Preconceptual Design Description for Caustic Recycle Facility

    SciTech Connect (OSTI)

    Sevigny, Gary J.; Poloski, Adam P.; Fountain, Matthew S.; Kurath, Dean E.

    2008-04-12

    The U.S. Department of Energy plans to vitrify both high-level and low-activity waste at the Hanford Site in southeastern Washington State. One aspect of the planning includes a need for a caustic recycle process to separate sodium hydroxide for recycle. Sodium is already a major limitation to the waste-oxide loading in the low-activity waste glass to be vitrified at the Waste Treatment Plant, and additional sodium hydroxide will be added to remove aluminum and to control precipitation in the process equipment. Aluminum is being removed from the high level sludge to reduce the number of high level waste canisters produced. A sodium recycle process would reduce the volume of low-activity waste glass produced and minimize the need to purchase new sodium hydroxide, so there is a renewed interest in investigating sodium recycle. This document describes an electrochemical facility for recycling sodium for the WTP.

  5. Solid Waste Program technical baseline description

    SciTech Connect (OSTI)

    Carlson, A.B.

    1994-07-01

    The system engineering approach has been taken to describe the technical baseline under which the Solid Waste Program is currently operating. The document contains a mission analysis, function analysis, system definition, documentation requirements, facility and project bases, and uncertainties facing the program.

  6. Property:Technology Description | Open Energy Information

    Open Energy Info (EERE)

    BEEN DEVELOPED FOR THIS OPTEC POWER IT IS THE ONLY RELIABLE AND PROFITABLE RENEWABLE ENERGY SOURCE FOR THE NEED OF WORLD ENERGY FOR THE NEXT DECADE DESALINATION AND HDROGEN...

  7. Acquisition Description/ Category Solicitation Method Contract...

    Energy Savers [EERE]

    ... Design, construction and operation of depleted Uranium Hexaflouride conversion facilities at Portsmouth and Paducah Babcock & Wilcox Conversion Services, LLC Full and Open ...

  8. Technical description of Stack 296-B-5

    SciTech Connect (OSTI)

    Ridge, T.M.

    1994-11-15

    Of particular concern to facilities on the Hanford site is Title 40, Code of Federal Regulations, Chapter 40, Part 61, Subpart H, ``National emission Standards for Emissions of Radionuclides Other Than Radon From Department of Energy Facilities.`` Assessments of facility stacks and potential radionuclide emissions determined whether these stacks would be subject to the sampling and monitoring requirements of 40 CFR 61, Subpart H. Stack 296-B-5 exhausts 221-BB building which houses tanks containing B Plant steam condensate and B Plant process condensate from the operation of the low-level waste concentrator. The assessment of potential radionuclide emissions from the 296-B-5 stack resulted in an effective dose equivalent to the maximally exposed individual of less than 0.1 millirem per year. Therefore, the stack is not subject to the sampling and monitoring requirements of 40 CFR 61, Subpart H. However, the sampling and monitoring system must be in compliance with the Environmental Compliance Manual, WHC-CM-7-5. Currently, 296-B-5 is sampled continuously with a record sampler and continuous air monitor (CAM).

  9. BSCProgramDescriptionDocumentJan2005.doc

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

    BALANCED SCORECARD PERFORMANCE MEASUREMENT AND PERFORMANCE MANAGEMENT PROGRAM FOR FEDERAL PROCUREMENT AND MANAGEMENT AND OPERATING CONTRACTOR PURCHASING SYSTEMS Revised: June 2016 ii PREFACE Over the past decade, the Department of Energy (DOE) has reengineered its programs for oversight of Federal and contractor procurement/purchasing systems, replacing Headquarters- based, process-oriented review programs with ones which rely on local assessment of performance against Departmental expectations.

  10. Property:Wavemaking Description | Open Energy Information

    Open Energy Info (EERE)

    driven selection of standard spectra or user specified DeFrees Large Wave Basin + Computer controlled 4m hydraulic wave paddle stroke allows a series of solitary waves to be...

  11. Property:Description | Open Energy Information

    Open Energy Info (EERE)

    Differential pressure transducers, acoustic profiling, propeller meters, load cells, computer data acquisition systems. Alden Small Flume + Differential pressure transducers,...

  12. BSCProgramDescriptionDocumentJan2005.doc

    Energy Savers [EERE]

    ... the Department of Energy Acquisition Regulation (DEAR) still requires compliance with ... DEAR Department of Energy Acquisition Regulation FASA Federal Acquisition Streamlining ...

  13. C# Software Title Software Description Date

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

    file reside in RAM. The generated list is unique to the vnfsroot provided on the command line. 1252010 10-014 C10040 HIV database SQL The code generates schema for HIV...

  14. C# Software Title Software Description Date

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

    Code (BLSCC), Version 1.x This software, written entirely in LabView, provides the command, control, and data acquisition capability for the BottleViz or CoilViz Bottle...

  15. Course Descriptions - Combustion Energy Frontier Research Center

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

    ... laser induced fluorescence, spontaneous Raman scattering, and new approaches to coherent anti-Stokes Raman spectroscopy. A lecture on laser physics will also be included. ...

  16. DISPOSAL CONTAINER HANDLING SYSTEM DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    E. F. Loros

    2000-06-30

    The Disposal Container Handling System receives and prepares new disposal containers (DCs) and transfers them to the Assembly Transfer System (ATS) or Canister Transfer System (CTS) for loading. The system receives the loaded DCs from ATS or CTS and welds the lids. When the welds are accepted the DCs are termed waste packages (WPs). The system may stage the WP for later transfer or transfer the WP directly to the Waste Emplacement/Retrieval System. The system can also transfer DCs/WPs to/from the Waste Package Remediation System. The Disposal Container Handling System begins with new DC preparation, which includes installing collars, tilting the DC upright, and outfitting the container for the specific fuel it is to receive. DCs and their lids are staged in the receipt area for transfer to the needed location. When called for, a DC is put on a cart and sent through an airlock into a hot cell. From this point on, all processes are done remotely. The DC transfer operation moves the DC to the ATS or CTS for loading and then receives the DC for welding. The DC welding operation receives loaded DCs directly from the waste handling lines or from interim lag storage for welding of the lids. The welding operation includes mounting the DC on a turntable, removing lid seals, and installing and welding the inner and outer lids. After the weld process and non-destructive examination are successfully completed, the WP is either staged or transferred to a tilting station. At the tilting station, the WP is tilted horizontally onto a cart and the collars removed. The cart is taken through an air lock where the WP is lifted, surveyed, decontaminated if required, and then moved into the Waste Emplacement/Retrieval System. DCs that do not meet the welding non-destructive examination criteria are transferred to the Waste Package Remediation System for weld preparation or removal of the lids. The Disposal Container Handling System is contained within the Waste Handling Building System. This includes the primary hot cell bounded by the receiving area and WP transport exit air locks; and isolation doors at ATS, CTS, and Waste Package Remediation. The hot cell includes areas for welding, various staging, tilting, and WP transporter loading. There are associated operating galleries and equipment maintenance areas outside the hot cell. These areas operate concurrently to accommodate the DC/WP throughput rates and support system maintenance. The new DC preparation area is located in an unshielded structure. The handling equipment includes DC/WP bridge cranes, tilting stations, and horizontal transfer carts. The welding area includes DC/WP welders and staging stations. Welding operations are supported by remotely operated equipment including a bridge crane and hoists, welder jib cranes, welding turntables, and manipulators. WP transfer includes a transfer/decontamination and transporter load area. The transfer operations are supported by a remotely operated horizontal lifting system, decontamination system, decontamination and inspection manipulator, and a WP horizontal transfer cart. All handling operations are supported by a suite of fixtures including collars, yokes, lift beams, and lid attachments. Remote equipment is designed to facilitate decontamination and maintenance. Interchangeable components are provided where appropriate. Set-aside areas are included, as required, for fixtures and tooling to support off-normal and recovery operations. Semi-automatic, manual, and backup control methods support normal, maintenance, and recovery operations. The system interfaces with the ATS and CTS to provide empty and receive loaded DCs. The Waste Emplacement/Retrieval System interfaces are for loading/unloading WPs on/from the transporter. The system also interfaces with the Waste Package Remediation System for DC/WP repair. The system is housed, shielded, supported, and has ventilation boundaries by the Waste Handling Building (WHB). The system is ventilated by the WHB Ventilation System, which in conjunction with ventilation boundaries ensure that ai

  17. WASTE PACKAGE REMEDIATION SYSTEM DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    N.D. Sudan

    2000-06-22

    The Waste Package Remediation System remediates waste packages (WPs) and disposal containers (DCs) in one of two ways: preparation of rejected DC closure welds for repair or opening of the DC/WP. DCs are brought to the Waste Package Remediation System for preparation of rejected closure welds if testing of the closure weld by the Disposal Container Handling System indicates an unacceptable, but repairable, welding flaw. DC preparation of rejected closure welds will require removal of the weld in such a way that the Disposal Container Handling System may resume and complete the closure welding process. DCs/WPs are brought to the Waste Package Remediation System for opening if the Disposal Container Handling System testing of the DC closure weld indicates an unrepairable welding flaw, or if a WP is recovered from the subsurface repository because suspected damage to the WP or failure of the WP has occurred. DC/WP opening will require cutting of the DC/WP such that a temporary seal may be installed and the waste inside the DC/WP removed by another system. The system operates in a Waste Package Remediation System hot cell located in the Waste Handling Building that has direct access to the Disposal Container Handling System. One DC/WP at a time can be handled in the hot cell. The DC/WP arrives on a transfer cart, is positioned within the cell for system operations, and exits the cell without being removed from the cart. The system includes a wide variety of remotely operated components including a manipulator with hoist and/or jib crane, viewing systems, machine tools for opening WPs, and equipment used to perform pressure and gas composition sampling. Remotely operated equipment is designed to facilitate DC/WP decontamination and hot cell equipment maintenance, and interchangeable components are provided where appropriate. The Waste Package Remediation System interfaces with the Disposal Container Handling System for the receipt and transport of WPs and DCs. The Waste Handling Building System houses the system, and provides the facility, safety, and auxiliary systems required to support operations. The system receives power from the Waste Handling Building Electrical System. The system also interfaces with the various DC systems.

  18. Site Acquisition Description/ Category Contracting Office Solicitation

    Office of Environmental Management (EM)

    ------------------------- Chapter 13.3 (March 2014) 1 [Reference: FAR Subpart 13. 3 and FAR Subpart 13.5] Simplified Acquisition Procedures 1. Introduction Simplified Acquisition Procedures (SAP) are contracting methods designed to streamline the acquisition process and facilitate the procurement of goods and services. The results include less paperwork and lower costs for both the contractor and the Government. FAR 13.003(a) states, "Agencies shall use simplified acquisition procedures to

  19. Site Acquisition Description/ Category Contracting Office Solicitation

    Office of Environmental Management (EM)

    222-S Lab Services http:www.emcbc.doe.g ovSEBhanfordlab EMCBC Small Business Fixed Price 40M-60M NA 2282014 12162013 642014 872014 5282015 Paducah Infrastructure...

  20. Product Service Codes @ Headquarters Description: Product Services...

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

    ... 1 7230 DRAPERIES, AWNINGS, AND SHADES 13,140.56 2 R708 SUPPORT- MANAGEMENT: PUBLICRELATIONS 13,000.00 1 X1AB LEASERENTAL OF CONFERENCE SPACE AND FACILITIES 12,734.30 1 ...

  1. C# Software Title Software Description Date

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

    The agent, while running, monitors for notifcation that it needs to upgrade using the DNS system to signal an update event. Upon receiving this signal the agent will download the...

  2. SC14_JLVayPosterDescription

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

    from first principles, and although the fundamentals of the PIC method were established decades ago, improvements or variations still continue to arise nearly continuously. ...

  3. INL Wind Farm Project Description Document

    SciTech Connect (OSTI)

    Gary Siefert

    2009-07-01

    The INL Wind Farm project proposes to install a 20 MW to 40 MW wind farm on government property, consisting of approximately ten to twenty full-sized (80-meter hub height) towers with 2 MW turbines, and access roads. This includes identifying the optimal turbine locations, building access roads, and pouring the tower foundations in preparation for turbine installation. The project successfully identified a location on INL lands with commercially viable wind resources (i.e., greater than 11 mph sustained winds) for a 20 to 40 MW wind farm. Additionally, the proposed Wind Farm was evaluated against other General Plant Projects, General Purpose Capital Equipment projects, and Line Item Construction Projects at the INL to show the relative importance of the proposed Wind Farm project.

  4. Description of Axial Detail for ROK Fuel

    SciTech Connect (OSTI)

    Trellue, Holly R; Galloway, Jack D

    2012-04-20

    For the purpose of NDA simulations of the ROK fuel assemblies, we have developed an axial burnup distribution to represent the pins themselves based on gamma scans of rods in the G23 assembly. For the purpose of modeling the G23 assembly (both at ORNL and LANL), the pin-by-pin burnup map as simulated by ROK is being assumed to represent the radial burnup distribution. However, both DA and NDA results indicate that this simulated estimate is not 100% correct. In particular, the burnup obtained from the axial gamma scan of 7 pins does not represent exactly the same 'average' pin burnup as the ROK simulation. Correction for this discrepancy is a goal of the well-characterized assembly task but will take time. For now, I have come up with a correlation for 26 axial points of the burnup as obtained by gamma scans of 7 different rods (C13, G01, G02, J11, K10, L02, and M04, neglecting K02 at this time) to the average burnup given by the simulation for each of the rods individually. The resulting fraction in each axial zone is then averaged for the 7 different rods so that it can represent every fuel pin in the assembly. The burnup in each of the 26 axial zones of rods in all ROK assemblies will then be directly adjusted using this fraction, which is given in Table 1. Note that the gamma scan data given by ROK for assembly G23 included a length of {approx}3686 mm, so the first 12 mm and the last 14 mm were ignored to give an actual rod length of {approx}366 cm. To represent assembly F02 in which no pin-by-pin burnup distribution is given by ROK, we must model it using infinitely-reflected geometry but can look at the effects of measuring in different axial zones by using intermediate burnup files (i.e. smaller burnups than 28 GWd/MTU) and determining which axial zone(s) each burnup represents. Details for assembly F02 are then given in Tables 2 and 3, which is given in Table 1 and has 44 total axial zones to represent the top meter in explicit detail in addition to the other 26 zones. Note that the MCNP files for F02 were created using the Monte Carlo burnup linkage code Monteburns, which saves MCNP input files with detailed compositions as a function of burnup. The 'intermediate burnup files' produced for F02 include a cooling time of 27 years. The axial location of 5 spacers was also included in the ROK F02 assembly in which each spacer contained a length of 3.81 cm. Note that due to the nature of Monteburns, which was run in a special fashion for this problem, the step number increments after the 27 year decay, so the second column of Table 2 refers to the step number that should be used in the Monteburns files.

  5. Physical Description and Experimental Characterization of the...

    Office of Scientific and Technical Information (OSTI)

    Resource Relation: Conference: APS March Metting held March 3 - February 7, 2014 in Denver, CO.; Related Information: Proposed for presentation at the APS March Metting held March ...

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

    Office of Scientific and Technical Information (OSTI)

    Conference Resource Relation: Conference: Presented at: 10th International Conference on Clustering Aspects of Nuclear Structure and Dynamics, Debrecen, Hungary, Sep 24 - Sep 28

  7. Waste Emplacement/Retrieval System Description Document

    SciTech Connect (OSTI)

    Eric Loros

    2001-07-25

    The Waste Emplacement/Retrieval System transports Waste Packages (WPs) from the Waste Handling Building (WHB) to the subsurface area of emplacement, and emplaces the WPs once there. The Waste Emplacement/Retrieval System also, if necessary, removes some or all of the WPs from the underground and transports them to the surface. Lastly, the system is designed to remediate abnormal events involving the portions of the system supporting emplacement or retrieval. During emplacement operations, the system operates on the surface between the WHB and North Portal, and in the subsurface in the North Ramp, access mains, and emplacement drifts. During retrieval or abnormal conditions, the operations areas may also extend to a surface retrieval storage site and South Portal on the surface, and the South Ramp in the subsurface. A typical transport and emplacement operation involves the following sequence of events. A WP is loaded into a WP transporter at the WHB, and coupled to a pair of transport locomotives. The locomotives transport the WP from the WHB, down the North Ramp, and to the entrance of an emplacement drift. Once docked at the entrance of the emplacement drift, the WP is moved outside of the WP transporter, and engaged by a WP emplacement gantry. The WP emplacement gantry lifts the WP, and transports it to its emplacement location, where the WP is then lowered to its final resting position. The WP emplacement gantry remains in the drift while the WP transporter is returned to the WHB by the locomotives. When the transporter reaches the WHB, the sequence of operations is repeated. Retrieval of all the WPs, or a large group of WPs, under normal conditions is achieved by reversing the emplacement operations. Retrieval of a small set of WPs, under normal or abnormal conditions, is known as recovery. Recovery performed under abnormal conditions will involve a suite of specialized equipment designed to perform a variety of tasks to enable the recovery process. Recovery after abnormal events may require clearing of equipment, rock, and ground support to facilitate recovery operations. Stabilization of existing ground support and installation of new ground support may also be needed. Recovery of WP(s) after an event that has contaminated drifts and/or WPs will require limiting the spread of contamination. Specialized equipment will also be necessary for system restoration (e.g., after a derailment, component failure). The Waste Emplacement/Retrieval System interfaces with the Subsurface Facility System and Ground Control System for the size and layout of the underground openings. The system interfaces with the Subsurface Ventilation System for the emplacement drift operating environment and the size of the drift isolation doors. The system interfaces with all WP types for the size, weight, and other important parameters affecting emplacement, recovery, and retrieval. The system interfaces with the Subsurface Emplacement Transportation System for the rail system upon which it operates and the distribution of power through the rail system. The system interfaces with the Monitored Geologic Repository (MGR) Operations Monitoring and Control System for the transmission of data to and from the system equipment, and for remote control of system equipment. The system interfaces with the Ground Control System for any repairs that are made. The system interfaces with the Emplacement Drift System for the WP emplacement mode and hardware. The system interfaces with the Disposal Container Handling System and the Waste Handling Building System for the receipt (during emplacement) and delivery (during retrieval/recovery) of WPs.

  8. Waste Emplacement/Retrieval System Description Document

    SciTech Connect (OSTI)

    2000-10-12

    The Waste Emplacement/Retrieval System transports Waste Packages (WPs) from the Waste Handling Building (WHB) to the subsurface area of emplacement, and emplaces the WPs once there. The system also, if necessary, removes some or all of the WPs from the underground and transports them to the surface. Lastly, the system is designed to remediate abnormal events involving the portions of the system supporting emplacement or retrieval. During emplacement operations, the system operates on the surface between the WHB and North Portal, and in the subsurface in the North Ramp, access mains, and emplacement drifts. During retrieval or abnormal conditions, the operations areas may also extend to a surface retrieval storage site and South Portal on the surface, and the South Ramp in the subsurface. A typical transport and emplacement operation involves the following sequence of events. A WP is loaded into a WP transporter at the WHB, and coupled to a pair of transport locomotives. The locomotives transport the WP from the WHB, down the North Ramp, and to the entrance of an emplacement drift. Once docked at the entrance of the emplacment drift, the WP is moved outside of the WP transporter, and engaged by a WP emplacement gantry. The gantry lifts the WP, and transports it to its emplacement location, where the WP is then lowered to its final resting position. The gantry remains in the drift while the WP transporter is returned to the WHB by the locomotives. When the transporter reaches the WHB, the sequence of operations is repeated. Retrieval of all the WPs, or a large group of WPs, under normal conditions is achieved by reversing the emplacement operations. Retrieval of a small set of WPs, under normal or abnormal conditions, is known as recovery. Recovery performed under abnormal conditions will involve a suite of specialized equipment designed to perform a variety of tasks to enable the recovery process. Recovery after abnormal events may require clearing of equipment, rock, and ground support to facilitate recovery operations. Stabilization of existing ground support and installation of new ground support may also be needed. Recovery of WPs after an event that has contaminated drifts and/or WPs will require limiting the spread of contamination. Specialized equipment will also be necessary for system restoration. The system interfaces with the Subsurface Facility System and Ground Control System for the size and layout of the underground openings. The system interfaces with the Subsurface Ventilation System for the emplacement drift operating environment and the size of the drift isolation doors. The system interfaces with all WP types for the size, weight, and other important parameters affecting emplacement, recovery, and retrieval. The system interfaces with the Subsurface Emplacement Transportation System for the rail system upon which it operates and the distribution of power throuch the rail system. The system interfaces with the Monitored Geologic Repository (MGR) Operations Monitoring and Control System for the transmission of data to and from the system equipment, and for remote control of system equipment. The system interfaces with the Ground Control System for any repairs that are made. The system interfaces with the Emplacement Drift System for the WP emplacement mode and hardware. The system interfaces with the Disposal Container Handling System and the Waste Handling Building System for the receipt (during emplacement) and delivery (during retrieval/recovery) of WPs.

  9. Site Acquisition Description/ Category Contracting Office Solicitation

    Office of Environmental Management (EM)

    Portsmouth Infrastructure https:www.emcbc.doe. govSEBPortsmouthISS EMCBC Small Business Fixed Price with Cost Plus Award 120-160M 7152014 722014 662014 1292014 3...

  10. Acquisition Description/ Category Solicitation Method Contract Type

    Office of Environmental Management (EM)

    Acknowledgments This report was prepared for the National Renewable Energy Laboratory (NREL) and funded by the U.S. Department of Energy's Office of Energy Efficiency and Renewable Energy, and the Permitting, Siting and Analysis Division of the Office of Electricity Delivery and Energy Reliability under National Renewable Energy Contract No. DE-AC36-08GO28308. The project was managed by Charles Kurnik of NREL. The Cadmus Group, Inc. managed protocols development with participation from a broad

  11. Machinist Pipeline/Apprentice Program Program Description

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

    cost effective than previous time-based programs Moves apprentices to journeyworker status more quickly Program Coordinator: Heidi Hahn Email: hahn@lanl.gov Phone number:...

  12. Gearbox Reliability Collaborative (GRC) Description and Loading

    SciTech Connect (OSTI)

    Oyague, F.

    2011-11-01

    This document describes simulated turbine load cases in accordance to the IEC 61400-1 Ed.3 standard, which is representative of the typical wind turbine design process. The information presented herein is intended to provide a broad understanding of the gearbox reliability collaborative 750kW drivetrain and turbine configuration. In addition, fatigue and ultimate strength drivetrain loads resulting from simulations are presented. This information provides the bases for the analytical work of the gearbox reliability collaborative effort.

  13. Acquisition Description/ Category Solicitation Method Contract...

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

    Professional Project Services, Inc. Safety and Ecology Corp. Terranear PMC-Energy Solutions ... Idaho NRC Spectra Tech, Inc. DE-SOL-0007515 Full and Open Competition ...

  14. DESCRIPTION OF THE SOFTWARE AND INTEGRATING PLATFORM

    SciTech Connect (OSTI)

    Flach, G.

    2009-12-31

    The Cementitious Barriers Partnership (CBP) Project is a multi-disciplinary, multi-institutional collaboration supported by the United States Department of Energy (US DOE) Office of Waste Processing. The objective of the CBP project is to develop a set of tools to improve understanding and prediction of the long-term structural, hydraulic, and chemical performance of cementitious barriers used in nuclear applications. A multi-disciplinary partnership of federal, academic, private sector, and international expertise has been formed to accomplish the project objective. In addition to the US DOE, the CBP partners are the Savannah River National Laboratory (SRNL), Vanderbilt University (VU)/Consortium for Risk Evaluation with Stakeholder Participation (CRESP), Energy Research Center of the Netherlands (ECN), and SIMCO Technologies, Inc. The Nuclear Regulatory Commission (NRC) is providing support under a Memorandum of Understanding. The National Institute of Standards and Technology (NIST) is providing research under an Interagency Agreement. Neither the NRC nor NIST are signatories to the CRADA. The periods of cementitious performance being evaluated are >100 years for operating facilities and > 1000 years for waste management. The set of simulation tools and data developed under this project will be used to evaluate and predict the behavior of cementitious barriers used in near surface engineered waste disposal systems, e.g., waste forms, containment structures, entombments, and environmental remediation, including decontamination and decommissioning analysis of structural concrete components of nuclear facilities (spent-fuel pools, dry spent-fuel storage units, and recycling facilities such as fuel fabrication, separations processes). Simulation parameters will be obtained from prior literature and will be experimentally measured under this project, as necessary, to demonstrate application of the simulation tools for three prototype applications (waste form in concrete vault, high-level waste tank grouting, and spent-fuel pool). Test methods and data needs to support use of the simulation tools for future applications will be defined. The CBP project is a five-year effort focused on reducing the uncertainties of current methodologies for assessing cementitious barrier performance and increasing the consistency and transparency of the assessment process. The results of this project will enable improved risk-informed, performance-based decision-making and support several of the strategic initiatives in the DOE Office of Environmental Management Engineering & Technology Roadmap. Those strategic initiatives include (1) enhanced tank closure processes; (2) enhanced stabilization technologies; (3) advanced predictive capabilities; (4) enhanced remediation methods; (5) adapted technologies for site-specific and complex-wide D&D applications; (6) improved SNF storage, stabilization and disposal preparation; (7) enhanced storage, monitoring and stabilization systems; and (8) enhanced long-term performance evaluation and monitoring.

  15. name NISAC description National Infrastructure Simulation and...

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

    wp namespaces oembed authentication routes namespace methods GET endpoints methods GET args context required false default view links self http www sandia gov nisac wp json oembed...

  16. Site Acquisition Description/ Category Contracting Office Solicitation

    Office of Environmental Management (EM)

    Hanford 222-S Lab Services http:www.emcbc.doe.g ovSEBhanfordlab EMCBC Small Business Fixed Price 40M-60M NA 2282014 12162013 642014 872014 5282015 Paducah...

  17. Site Acquisition Description/ Category Contracting Office Solicitation

    Office of Environmental Management (EM)

    PPPO GDP DUF6 https:www.emcbc.doe. govSEBDUF6 EMCBC Full and Open Competition CPAFFP 400M- 600M 4282015 412015 692015 982015 11242015 May-Jul 2016 Los Alamos ...

  18. K Basin sludge treatment process description

    SciTech Connect (OSTI)

    Westra, A.G.

    1998-08-28

    The K East (KE) and K West (KW) fuel storage basins at the 100 K Area of the Hanford Site contain sludge on the floor, in pits, and inside fuel storage canisters. The major sources of the sludge are corrosion of the fuel elements and steel structures in the basin, sand intrusion from outside the buildings, and degradation of the structural concrete that forms the basins. The decision has been made to dispose of this sludge separate from the fuel elements stored in the basins. The sludge will be treated so that it meets Tank Waste Remediation System (TWRS) acceptance criteria and can be sent to one of the double-shell waste tanks. The US Department of Energy, Richland Operations Office accepted a recommendation by Fluor Daniel Hanford, Inc., to chemically treat the sludge. Sludge treatment will be done by dissolving the fuel constituents in nitric acid, separating the insoluble material, adding neutron absorbers for criticality safety, and reacting the solution with caustic to co-precipitate the uranium and plutonium. A truck will transport the resulting slurry to an underground storage tank (most likely tank 241-AW-105). The undissolved solids will be treated to reduce the transuranic (TRU) and content, stabilized in grout, and transferred to the Environmental Restoration Disposal Facility (ERDF) for disposal. This document describes a process for dissolving the sludge to produce waste streams that meet the TWRS acceptance criteria for disposal to an underground waste tank and the ERDF acceptance criteria for disposal of solid waste. The process described is based on a series of engineering studies and laboratory tests outlined in the testing strategy document (Flament 1998).

  19. Low-Cost Spectral Sensor Development Description.

    SciTech Connect (OSTI)

    Armijo, Kenneth Miguel; Yellowhair, Julius

    2014-11-01

    Solar spectral data for all parts of the US is limited due in part to the high cost of commercial spectrometers. Solar spectral information is necessary for accurate photovoltaic (PV) performance forecasting, especially for large utility-scale PV installations. A low-cost solar spectral sensor would address the obstacles and needs. In this report, a novel low-cost, discrete- band sensor device, comprised of five narrow-band sensors, is described. The hardware is comprised of commercial-off-the-shelf components to keep the cost low. Data processing algorithms were developed and are being refined for robustness. PV module short-circuit current ( I sc ) prediction methods were developed based on interaction-terms regression methodology and spectrum reconstruction methodology for computing I sc . The results suggest the computed spectrum using the reconstruction method agreed well with the measured spectrum from the wide-band spectrometer (RMS error of 38.2 W/m 2 -nm). Further analysis of computed I sc found a close correspondence of 0.05 A RMS error. The goal is for ubiquitous adoption of the low-cost spectral sensor in solar PV and other applications such as weather forecasting.

  20. Site Acquisition Description/ Category Contracting Office Solicitation

    Office of Environmental Management (EM)

    Range Pre-Solicitation Conference Industry Meetings Draft- Solicitation Synopsis Solicitation Receipt of Proposal Anticipated Evaluations CompleteAward Paducah GDP http:...

  1. Site Acquisition Description/ Category Contracting Office Solicitation

    Office of Environmental Management (EM)

    Range Pre-Solicitation Conference Industry Meetings Draft- Solicitation Synopsis Solicitation Receipt of Proposal Anticipated Evaluations CompleteAward Headquarters Information ...

  2. 207-A retention basins system design description

    SciTech Connect (OSTI)

    Wahlquist, R.A.

    1994-09-29

    The 242-A Evaporator is a waste treatment facility designed to reduce liquid waste volumes currently stored in the Hanford Area double shell Waste Storage Tanks. The evaporator uses evaporative concentration to achieve this volume reduction, returning the concentrated slurry to the double-shell tanks for storage. The process effluent is transferred to various retention/treatment facilities for eventual release to the environment. The process utilizes an evaporator vessel and various supporting systems for heating, evaporating, and condensing low-heat-generating liquid waste produced it the Hanford Site. The process reduces the total volume of the liquid waste requiring storage in a double shell tank, making it more manageable for current storage as well as for future treatment and disposal. The main components of the 242-A Evaporator are the Reboiler, Vapor-Liquid Separator, Recirculation Pump and Pump Loop, Slurry System, Condenser System, Steam Jet Vacuum System, Condensate Collection Tank, and Ion Exchange System.

  3. Acquisition Description/ Category Solicitation Method Contract...

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

    ... Moab Remedial Action Contract (Uranium Mill Tailings Cleanup) Portage, Inc. Competitive Small Business IDIQ Task Order Cost Plus Award Fee wFixed Unit Price Component 110411-09...

  4. Site Acquisition Description/ Category Contracting Office Solicitation

    Office of Environmental Management (EM)

    Laboratory Follow- On Procurements https:www.emcbc.doe. govSEBLANLPostFY1 6index.php EMCBC Full and Open Competition CPAF 500M-1B 2015 2016 2016 2016 2016 2016 Savannah...

  5. Microsoft Word - HQ ISM System Description Final

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

    ... analysis, solution planning, and solution implementation. ... both trends in performance excellence an emerging problems. ... N required HQ Emergency Operations Center involvement. NA-40 ...

  6. Theoretical Description of the Fission Process

    SciTech Connect (OSTI)

    Witold Nazarewicz

    2009-10-25

    Advanced theoretical methods and high-performance computers may finally unlock the secrets of nuclear fission, a fundamental nuclear decay that is of great relevance to society. In this work, we studied the phenomenon of spontaneous fission using the symmetry-unrestricted nuclear density functional theory (DFT). Our results show that many observed properties of fissioning nuclei can be explained in terms of pathways in multidimensional collective space corresponding to different geometries of fission products. From the calculated collective potential and collective mass, we estimated spontaneous fission half-lives, and good agreement with experimental data was found. We also predicted a new phenomenon of trimodal spontaneous fission for some transfermium isotopes. Our calculations demonstrate that fission barriers of excited superheavy nuclei vary rapidly with particle number, pointing to the importance of shell effects even at large excitation energies. The results are consistent with recent experiments where superheavy elements were created by bombarding an actinide target with 48-calcium; yet even at high excitation energies, sizable fission barriers remained. Not only does this reveal clues about the conditions for creating new elements, it also provides a wider context for understanding other types of fission. Understanding of the fission process is crucial for many areas of science and technology. Fission governs existence of many transuranium elements, including the predicted long-lived superheavy species. In nuclear astrophysics, fission influences the formation of heavy elements on the final stages of the r-process in a very high neutron density environment. Fission applications are numerous. Improved understanding of the fission process will enable scientists to enhance the safety and reliability of the nations nuclear stockpile and nuclear reactors. The deployment of a fleet of safe and efficient advanced reactors, which will also minimize radiotoxic waste and be proliferation-resistant, is a goal for the advanced nuclear fuel cycles program. While in the past the design, construction, and operation of reactors were supported through empirical trials, this new phase in nuclear energy production is expected to heavily rely on advanced modeling and simulation capabilities.

  7. IHE material qualification tests description and criteria

    SciTech Connect (OSTI)

    Slape, R J

    1984-06-01

    This report describes the qualification tests presently being used at Pantex Plant, Lawrence Livermore National Laboratory, and Los Alamos National Laboratory that are required by the Department of Energy prior to the approval for an explosive as an Insensitive High Explosive (IHE) material. The acceptance criteria of each test for IHE qualification is also discussed. 5 references, 10 figures.

  8. Galilei invariant technique for quantum system description

    SciTech Connect (OSTI)

    Kamuntavi?ius, Gintautas P.

    2014-04-15

    Problems with quantum systems models, violating Galilei invariance are examined. The method for arbitrary non-relativistic quantum system Galilei invariant wave function construction, applying a modified basis where center-of-mass excitations have been removed before Hamiltonian matrix diagonalization, is developed. For identical fermion system, the Galilei invariant wave function can be obtained while applying conventional antisymmetrization methods of wave functions, dependent on single particle spatial variables.

  9. Waste management project technical baseline description

    SciTech Connect (OSTI)

    Sederburg, J.P.

    1997-08-13

    A systems engineering approach has been taken to describe the technical baseline under which the Waste Management Project is currently operating. The document contains a mission analysis, function analysis, requirement analysis, interface definitions, alternative analysis, system definition, documentation requirements, implementation definitions, and discussion of uncertainties facing the Project.

  10. ACTION DESCRIPTION MEMORANDUM PROPOSED DECONTAMINATION OF THREE...

    Office of Legacy Management (LM)

    ... of about 400 ha (1000 acres) and is a residential community of more than 45,000 people, ... As part of FUSRAP, the U.S. Department of Energy, Oak Ridge Operations, is proposing to ...

  11. Density functional description of Coulomb blockade: Adiabatic...

    Office of Scientific and Technical Information (OSTI)

    This content will become publicly available on June 29, 2016 Prev Next Title: ... will become publicly available on June 29, 2016 Publisher's Version of Record 10.1103...

  12. CATEGORICAL EXCLUSION (CX) DETERMINATION BRIEF DESCRIPTION OF...

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

    OF PROPOSED ACTION: Southwestern Power Administration proposes to perform aerial saw tree trimming activities along select portions of transmission line rights-of-ways located...

  13. Site Acquisition Description/ Category Contracting Office Solicitation

    Office of Environmental Management (EM)

    Idaho Calcine Disposition Project A&E https:www.emcbc.doe. govSEBCDP EMCBC Full and ... on the DOE Acquisition Forecast (http:hqlnc.doe.govForecast) and other public sources. ...

  14. High Consequence System Surety process description

    SciTech Connect (OSTI)

    Randall, G.T.

    1995-09-01

    This report documents work-in-progress accomplished prior to programmatic changes that negated bringing this effort to conclusion as originally intended. The High Consequence System Surety (HCS{sup 2}) project pulls together a multi-disciplinary team to integrate the elements of surety safety, security, control, reliability and quality--into a new, encompassing process. The benefit of using this process is enhanced surety in the design of a high consequence system through an up-front, designed-in approach. This report describes the integrated, high consequence surety process and includes a hypothetical example to illustrate the process.

  15. BSCProgramDescriptionDocumentJan2005.doc

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

    ... to ensure the: (1) Acquisition of quality products and services at fair and reasonable prices; (2) Use of capable and reliable subcontractors who either (i) Have track records ...

  16. DOE Tribal Clean Energy Project Descriptions

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

    DOE Award Project Location Project Focus Feasibility Study Tlingit Haida Regional Housing Authority (THRHA) $898,772 Juneau, AK The project will provide energy assessments, alternative energy monitoring, and energy conservation upgrades for low-income, multi-family residences in 14 southeast Alaska communities with extremely high energy costs. THRHA will also provide home energy assessments, energy conservation education, and energy use monitoring for 400 families. Confederated Salish and

  17. SITE ELECTRICAL POWER SYSTEM DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    E.P. McCann

    1999-04-16

    The Site Electrical Power System receives and distributes utility power to all North Portal site users. The major North Portal users are the Protected Area including the subsurface facility and Balance of Plant areas. The system is remotely monitored and controlled from the Surface Operations Monitoring and Control System. The system monitors power quality and provides the capability to transfer between Off-Site Utility and standby power (including dedicated safeguards and security power). Standby power is only distributed to selected loads for personnel safety and essential operations. Security power is only distributed to essential security operations. The standby safeguards and security power is independent from all other site power. The system also provides surface lighting, grounding grid, and lightning protection for the North Portal. The system distributes power during construction, operation, caretaker, and closure phases of the repository. The system consists of substation equipment (disconnect switches, breakers, transformers and grounding equipment) and power distribution cabling from substation to the north portal switch gear building. Additionally, the system includes subsurface facility substation (located on surface), switch-gear, standby diesel generators, underground duct banks, power cables and conduits, switch-gear building and associated distribution equipment for power distribution. Each area substation distributes power to the electrical loads and includes the site grounding, site lighting and lightning protection equipment. The site electrical power system distributes power of sufficient quantity and quality to meet users demands. The Site Electrical Power System interfaces with the North Portal surface systems requiring electrical power. The system interfaces with the Subsurface Electrical Distribution System which will supply power to the underground facilities from the North Portal. Power required for the South Portal and development side activities of the subsurface facility will be provided at the South Portal by the Subsurface Electrical Distribution System. The Site Electrical Power System interfaces with the Off-Site Utility System for the receipt of power. The System interfaces with the Surface Operations Monitoring and Control System for monitoring and control. The System interfaces with MGR Site Layout System for the physical location of equipment and power distribution.

  18. Idaho National Laboratory Description, Chellenges, Technology...

    Office of Environmental Management (EM)

    ... * Encapsulation of corroded fuel cladding, hulls, pins etc. * Immobilization of ... Iodine, ... * DOE-ID currently has a HIP unit installed in the HFEF hot-cell at INL ...

  19. Descriptive Morphology Terms For MAMA software

    SciTech Connect (OSTI)

    Ruggiero, Christy E.; Porter, Reid B.

    2014-05-21

    The table on the following pages lists a set of morphology terms for describing materials. We have organized these terms by categories. Software uses are welcome to suggest other terms that are needed to accurately describe materials. This list is intended as a initial starting point to generating a consensus terminology list.

  20. Microsoft Word - ISDAC_description.doc

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

    Facility's (ACRF) North Slope of Alaska (NSA) locale for three weeks in April 2008. This ... surface-based measurements at the ACRF NSA locale provide retrievals of aerosol, ...

  1. SSL Selections Descriptions v6.xls

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

    General Electric Niskayuna, NY 12309-1027 Optimized Phosphors for Warm-White LED Light Engines. GE Global Research, in collaboration with GE Lumination and the University of ...

  2. BSCProgramDescriptionDocumentJan2005.doc

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

    major contractors, have an enabling or a constraining role, but will rarely be the primary objective for business systems. Success for such organizations should be measured by...

  3. Property:File/Description | Open Energy Information

    Open Energy Info (EERE)

    + Map of the U.S. land-based and offshore annual average wind speed at 100m B BOEMRE OCS.oil.gas.2007-12.map.pdf + Outer Continental Shelf (OCS) Oil & Gas Leasing Program 2007 -...

  4. Integrated Safety Management System (ISMS) program description

    SciTech Connect (OSTI)

    BUMP, S.L.

    1999-09-30

    This document the ISMS Program for the 300 Area and lists the procedures necessary to implement the program.

  5. Screening Analysis : Volume 1, Description and Conclusions.

    SciTech Connect (OSTI)

    Bonneville Power Administration; Corps of Engineers; Bureau of Reclamation

    1992-08-01

    The SOR consists of three analytical phases leading to a Draft EIS. The first phase Pilot Analysis, was performed for the purpose of testing the decision analysis methodology being used in the SOR. The Pilot Analysis is described later in this chapter. The second phase, Screening Analysis, examines all possible operating alternatives using a simplified analytical approach. It is described in detail in this and the next chapter. This document also presents the results of screening. The final phase, Full-Scale Analysis, will be documented in the Draft EIS and is intended to evaluate comprehensively the few, best alternatives arising from the screening analysis. The purpose of screening is to analyze a wide variety of differing ways of operating the Columbia River system to test the reaction of the system to change. The many alternatives considered reflect the range of needs and requirements of the various river users and interests in the Columbia River Basin. While some of the alternatives might be viewed as extreme, the information gained from the analysis is useful in highlighting issues and conflicts in meeting operating objectives. Screening is also intended to develop a broad technical basis for evaluation including regional experts and to begin developing an evaluation capability for each river use that will support full-scale analysis. Finally, screening provides a logical method for examining all possible options and reaching a decision on a few alternatives worthy of full-scale analysis. An organizational structure was developed and staffed to manage and execute the SOR, specifically during the screening phase and the upcoming full-scale analysis phase. The organization involves ten technical work groups, each representing a particular river use. Several other groups exist to oversee or support the efforts of the work groups.

  6. C# Software Title Software Description Date

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

    IP. Windows OS only; designed for the Glovebox Unattended Assay and Monitoring Data Acquisition and Review (GDAR) system. See GUAM Data Acquisition and Review, LANLN-1, (Oct....

  7. Numerical description of cavitation on axisymmetric bodies

    SciTech Connect (OSTI)

    Hickox, C.E.; Hailey, C.E.; Wolfe, W.P.; Watts, H.A.; Gross, R.J.; Ingber, M.S.

    1988-01-01

    This paper reports on ongoing studies which are directed toward the development of predictive techniques for the modeling of steady cavitation on axisymmetric bodies. The primary goal of the modeling effort is the prediction of cavity shape and pressure distribution from which forces and moments can be calculated. Here we present an overview of the modeling techniques developed and compare predictions with experimental data obtained from water tunnel tests for both limited and supercavitation. 14 refs., 4 figs.

  8. Certificate in Environmental Monitoring Program Description

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

    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...

  9. Hydrogeologic investigation and establishment of a permanent multi-observational well network in Aiken, Allendale, and Barnwell Counties, South Carolina. Eight-year interim report (1986-1994). Volume 1 cluster-site description

    SciTech Connect (OSTI)

    Gellici, J.A.; Reed, R.H.; Logan, W.R.; Aadland, R.K.; Simones, G.C.

    1995-05-01

    The South Carolina Department of Natural Resources, Water Resources Division (SCWRD), in collaboration with the United States Department of Energy (USDOE) is conducting a hydrogeologic investigation of the ground-water system(s) peripheral to the Savannah River Site. The study area is located in the Southeastern Coastal Plain hydrogeologic province in Aiken, Allendale and Barnwell Counties, South Carolina. Ground-water movement, quality, and availability are being evaluated in order to better protect and manage this valuable regional resource. The investigation involves a well-cluster system comparable to the one constructed on the SRS. Cluster sites are situated outside the SRS on the basis of study objectives, proximity to the plant`s borders, land availability, and for the optimization of hydrogeologic control. One to three wells are completed into each major aquifer, and at each cluster site, at least one borehole is continuously cored and geophysically logged from land surface to at least 10 feet into unweathered bedrock. Data collected from the ongoing study include 146 paleontologic and palynologic age dates, 100 x-ray diffraction analyses of clay and bulk mineralogy, 442 sieve analyses, 6,040 feet of detailed core description, mineral composition and porosity determined from thin-section analyses, and continuous water-level data. This report is a compilation and interpretation of the {open_quotes}C-well{close_quotes} data that have been generated from the project and that will be used to model and characterize the aquifers and confining units in the region.

  10. Studies of acute and chronic radiation injury at the Biological and Medical Research Division, Argonne National Laboratory, 1953-1970: Description of individual studies, data files, codes, and summaries of significant findings

    SciTech Connect (OSTI)

    Grahn, D.; Fox, C.; Wright, B.J.; Carnes, B.A.

    1994-05-01

    Between 1953 and 1970, studies on the long-term effects of external x-ray and {gamma} irradiation on inbred and hybrid mouse stocks were carried out at the Biological and Medical Research Division, Argonne National Laboratory. The results of these studies, plus the mating, litter, and pre-experimental stock records, were routinely coded on IBM cards for statistical analysis and record maintenance. Also retained were the survival data from studies performed in the period 1943-1953 at the National Cancer Institute, National Institutes of Health, Bethesda, Maryland. The card-image data files have been corrected where necessary and refiled on hard disks for long-term storage and ease of accessibility. In this report, the individual studies and data files are described, and pertinent factors regarding caging, husbandry, radiation procedures, choice of animals, and other logistical details are summarized. Some of the findings are also presented. Descriptions of the different mouse stocks and hybrids are included in an appendix; more than three dozen stocks were involved in these studies. Two other appendices detail the data files in their original card-image format and the numerical codes used to describe the animal`s exit from an experiment and, for some studies, any associated pathologic findings. Tabular summaries of sample sizes, dose levels, and other variables are also given to assist investigators in their selection of data for analysis. The archive is open to any investigator with legitimate interests and a willingness to collaborate and acknowledge the source of the data and to recognize appropriate conditions or caveats.

  11. International petroleum statistics report

    SciTech Connect (OSTI)

    1996-03-01

    This report presents data on international oil production, demand, imports, exports, and stocks. World oil production and OECD demand data are for the years 1970 through 1994; OECD stocks from 1973 through 1994; and OECD trade from 1984 through 1994.

  12. Energy & Financial Markets - Crudeoil - U.S. Energy Information

    Gasoline and Diesel Fuel Update (EIA)

    Administration (EIA) OECD The Organization of Economic Cooperation and Development (OECD) consists of the United States, much of Europe, and other advanced countries. At 53 percent of world oil consumption in 2010, these large economies consume more oil than the non-OECD countries, but have much lower oil consumption growth. Oil consumption in the OECD countries actually declined in the decade between 2000 and 2010, whereas non-OECD consumption rose 40 percent during the same period. In OECD

  13. ENV-Linkages General Equilibrium Model | Open Energy Information

    Open Energy Info (EERE)

    Topics: Co-benefits assessment Resource Type: Softwaremodeling tools Website: www.oecd.orgofficialdocumentsdisplaydocumentpdf?coteECOWKP(2008)6 References: OECD1...

  14. Word Pro - S11

    Gasoline and Diesel Fuel Update (EIA)

    ... U.S. Territories; for 1984 forward, Mexico; and, for 2000 forward, Chile, Estonia, and Israel. d The Organization for Economic Cooperation and Development (OECD) consists of "OECD ...

  15. Analysis of the OECD/NRC BWR Turbine Trip Transient Benchmark with the Coupled Thermal-Hydraulics and Neutronics Code TRAC-M/PARCS

    SciTech Connect (OSTI)

    Lee, Deokjung; Downar, Thomas J.; Ulses, Anthony; Akdeniz, Bedirhan; Ivanov, Kostadin N.

    2004-10-15

    An analysis of the Peach Bottom Unit 2 Turbine Trip 2 (TT2) experiment has been performed using the U.S. Nuclear Regulatory Commission coupled thermal-hydraulics and neutronics code TRAC-M/PARCS. The objective of the analysis was to assess the performance of TRAC-M/PARCS on a BWR transient with significance in two-phase flow and spatial variations of the neutron flux. TRAC-M/PARCS results are found to be in good agreement with measured plant data for both steady-state and transient phases of the benchmark. Additional analyses of four fictitious extreme scenarios are performed to provide a basis for code-to-code comparisons and comprehensive testing of the thermal-hydraulics/neutronics coupling. The obtained results of sensitivity studies on the effect of direct moderator heating on transient simulation indicate the importance of this modeling aspect.

  16. Using the OECD/NRC Pressurized Water Reactor Main Steam Line Break Benchmark to Study Current Numerical and Computational Issues of Coupled Calculations

    SciTech Connect (OSTI)

    Ivanov, Kostadin N.; Todorova, Nadejda K.; Sartori, Enrico

    2003-05-15

    Incorporating full three-dimensional (3-D) models of the reactor core into system transient codes allows for a 'best-estimate' calculation of interactions between the core behavior and plant dynamics. Recent progress in computer technology has made the development of coupled thermal-hydraulic (T-H) and neutron kinetics code systems feasible. Considerable efforts have been made in various countries and organizations in this direction. Appropriate benchmarks need to be developed that will permit testing of two particular aspects. One is to verify the capability of the coupled codes to analyze complex transients with coupled core-plant interactions. The second is to test fully the neutronics/T-H coupling. One such benchmark is the Pressurized Water Reactor Main Steam Line Break (MSLB) Benchmark problem. It was sponsored by the Organization for Economic Cooperation and Development, U.S. Nuclear Regulatory Commission, and The Pennsylvania State University. The benchmark problem uses a 3-D neutronics core model that is based on real plant design and operational data for the Three Mile Island Unit 1 nuclear power plant. The purpose of this benchmark is threefold: to verify the capability of system codes for analyzing complex transients with coupled core-plant interactions; to test fully the 3-D neutronics/T-H coupling; and to evaluate discrepancies among the predictions of coupled codes in best-estimate transient simulations. The purposes of the benchmark are met through the application of three exercises: a point kinetics plant simulation (exercise 1), a coupled 3-D neutronics/core T-H evaluation of core response (exercise 2), and a best-estimate coupled core-plant transient model (exercise 3).In this paper we present the three exercises of the MSLB benchmark, and we summarize the findings of the participants with regard to the current numerical and computational issues of coupled calculations. In addition, this paper reviews in some detail the sensitivity studies on exercises 2 and 3 performed by the benchmark team using the coupled code TRAC-PF1/NEM. The purpose of these supporting studies was to aid participants in developing their models.

  17. Evaluation of select heat and pressure measurement gauges for potential use in the NRC/OECD High Energy Arc Fault (HEAF) test program.

    SciTech Connect (OSTI)

    Lopez, Carlos; Wente, William Baker; Figueroa, Victor G.

    2014-01-01

    In an effort to improve the current state of the art in fire probabilistic risk assessment methodology, the U.S. Nuclear Regulatory Commission, Office of Regulatory Research, contracted Sandia National Laboratories (SNL) to conduct a series of scoping tests to identify thermal and mechanical probes that could be used to characterize the zone of influence (ZOI) during high energy arc fault (HEAF) testing. For the thermal evaluation, passive and active probes were exposed to HEAF-like heat fluxes for a period of 2 seconds at the SNLs National Solar Thermal Test Facility to determine their ability to survive and measure such an extreme environment. Thermal probes tested included temperature lacquers (passive), NANMAC thermocouples, directional flame thermometers, modified plate thermometers, infrared temperature sensors, and a Gardon heat flux gauge. Similarly, passive and active pressure probes were evaluated by exposing them to pressures resulting from various high-explosive detonations at the Sandia Terminal Ballistic Facility. Pressure probes included bikini pressure gauges (passive) and pressure transducers. Results from these tests provided good insight to determine which probes should be considered for use during future HEAF testing.

  18. Energy & Financial Markets - U.S. Energy Information Administration (EIA) -

    Gasoline and Diesel Fuel Update (EIA)

    U.S. Energy Information Administration (EIA) OECD The Organization of Economic Cooperation and Development (OECD) consists of the United States, much of Europe, and other advanced countries. At 53 percent of world oil consumption in 2010, these large economies consume more oil than the non-OECD countries, but have much lower oil consumption growth. Oil consumption in the OECD countries actually declined in the decade between 2000 and 2010, whereas non-OECD consumption rose 40 percent during

  19. NALWO Playgroup

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

    Description: Description: AFS.rootfnalfileswwwdocsorgsnalwonalwoheader.gif Description: Description: home Description: Description: about Fermilab Description:...

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

    Office of Scientific and Technical Information (OSTI)

    Physics Opportunities of a Fixed Target Experiment using the LHC Beams Brodsky S J SLAC Fleuret F Ecole Polytechnique Hadjidakis C Lansberg J P Orsay IPN HYDROGEN ASYMMETRY BOSONS...

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

    Office of Scientific and Technical Information (OSTI)

    Open problems in condensed matter physics Falicov L M CONDENSED MATTER PHYSICS SUPERCONDUCTIVITY AND SUPERFLUIDITY SOLID STATE PHYSICS RESEARCH PROGRAMS SUPERCONDUCTIVITY CRITICAL...

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

    Office of Scientific and Technical Information (OSTI)

    Quarkonium Physics at a Fixed Target Experiment Using the LHC Beams Lansberg J P Orsay IPN Brodsky S J SLAC Fleuret F Ecole Polytechnique Hadjidakis C Orsay IPN PHYSICS OF...

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

    Office of Scientific and Technical Information (OSTI)

    State University NCSU which ATP has licensed could be feasibly deployed in a mobile unit The study adds to the area investigated by having ATP s STTR Phase I team give...

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

    Office of Scientific and Technical Information (OSTI)

    OL Operable Unit Pilot Study XRF Evaluation of Select Pre Hanford Orchards Bunn Amoret L Fritz Brad G Pulsipher Brent A Gorton Alicia M Bisping Lynn E Brandenberger Jill M Pino...

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

    Office of Scientific and Technical Information (OSTI)

    c exceeds K and this enhanced superconductivity is also shown to originate from a to unit cell thick interfacial layer The results demonstrate that engineering artificial...

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

    Office of Scientific and Technical Information (OSTI)

    in the orthorhombic space group i Immm i No Z with a b and c pm This is a standardized unit cell of the previously published La Al structure type Wavelength dispersive microprobe...

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

    Office of Scientific and Technical Information (OSTI)

    Re evaluation of Spent Nuclear Fuel Assay Data for the Three Mile Island Unit Reactor and Application to Code Validation Gauld Ian C Oak Ridge National Lab ORNL Oak Ridge TN United...

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

    Office of Scientific and Technical Information (OSTI)

    limits for hydrochloric acid than the reference method Results from a dry stack unit had better comparability between methods than results from a wet stack unit This result...

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

    Office of Scientific and Technical Information (OSTI)

    Nye County Nevada The text of the report summarizes data for each stratigraphic unit examined Checklists for tabulating field data at each locale are included in an...

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

    Office of Scientific and Technical Information (OSTI)

    to coal derived syngas produced in the pilot scale transport reactor development unit TRDU Western Research Institute WRI with funding from the State of Wyoming Clean Coal...

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

    Office of Scientific and Technical Information (OSTI)

    distillation for new plants A design concept for a modular microchannel distillation unit was developed in Task In Task Ultrasonic Additive Machining UAM was evaluated as a...

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

    Office of Scientific and Technical Information (OSTI)

    were conducted at the laboratory scale to examine sorbents for their CO sub capacity conversion of CO to CO sub and impacts of adsorption and regeneration conditions and...

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

    Office of Scientific and Technical Information (OSTI)

    Mechanical properties and energy absorption characteristics of a polyurethane foam Goods S H Neuschwanger C L Henderson C Skala D M MATERIALS SCIENCE FOAMS MECHANICAL PROPERTIES...

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

    Office of Scientific and Technical Information (OSTI)

    Energy Dissipation in the Target Station of the Spallation Neutron Source Charlton L A Difilippo F C PARTICLE ACCELERATORS MATHEMATICS COMPUTERS INFORMATION SCIENCE MANAGEMENT LAW...

  15. Sodium storage facility trace heat system design description

    SciTech Connect (OSTI)

    Jones, D.D.

    1997-06-12

    This document describes the SSF PLC Ladder Logic, Cross references, and the software that was used to control the amount of power applied to the SSF Trace Heated components.

  16. Telemedicine system interoperability architecture: concept description and architecture overview.

    SciTech Connect (OSTI)

    Craft, Richard Layne, II

    2004-05-01

    In order for telemedicine to realize the vision of anywhere, anytime access to care, it must address the question of how to create a fully interoperable infrastructure. This paper describes the reasons for pursuing interoperability, outlines operational requirements that any interoperability approach needs to consider, proposes an abstract architecture for meeting these needs, identifies candidate technologies that might be used for rendering this architecture, and suggests a path forward that the telemedicine community might follow.

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

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

    ... NREL's credentials are beyond reproach and NREL is viewed as a definitive resource on energy technology, policy, and market matters. NREL's energy technology, policy, and market ...

  18. Nuclear Waste Partnership (NWP) Quality Assurance Program Description (QAPD)

    Broader source: Energy.gov [DOE]

    Supporting Technical Document for the Radiological Release Accident Investigation Report (Phase II Report)

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

    Office of Scientific and Technical Information (OSTI)

    geothermal application Cuderman J F Chu T Y Jung J Jacobson R D GEOTHERMAL ENERGY NATURAL GAS PETROLEUM GEOSCIENCES BOREHOLES EXPLOSIVE FRACTURING TUFF EXPERIMENTAL DATA...

  20. Shell model description of band structure in 48Cr

    SciTech Connect (OSTI)

    Vargas, Carlos E.; Velazquez, Victor M.

    2007-02-12

    The band structure for normal and abnormal parity bands in 48Cr are described using the m-scheme shell model. In addition to full fp-shell, two particles in the 1d3/2 orbital are allowed in order to describe intruder states. The interaction includes fp-, sd- and mixed matrix elements.