National Library of Energy BETA

Sample records for line accidents storage

  1. Canister Storage Building (CSB) Design Basis Accident Analysis Documentation

    SciTech Connect (OSTI)

    CROWE, R.D.; PIEPHO, M.G.

    2000-03-23

    This document provided the detailed accident analysis to support HNF-3553, Spent Nuclear Fuel Project Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report''. All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.

  2. Three dimensional effects in analysis of PWR steam line break accident

    E-Print Network [OSTI]

    Tsai, Chon-Kwo

    A steam line break accident is one of the possible severe abnormal transients in a pressurized water reactor. It is required to present an analysis of a steam line break accident in the Final Safety Analysis Report (FSAR) ...

  3. Technical evaluation: 300 Area steam line valve accident

    SciTech Connect (OSTI)

    Not Available

    1993-08-01

    On June 7, 1993, a journeyman power operator (JPO) was severely burned and later died as a result of the failure of a 6-in. valve that occurred when he attempted to open main steam supply (MSS) valve MSS-25 in the U-3 valve pit. The pit is located northwest of Building 331 in the 300 Area of the Hanford Site. Figure 1-1 shows a layout of the 300 Area steam piping system including the U-3 steam valve pit. Figure 1-2 shows a cutaway view of the approximately 10- by 13- by 16-ft-high valve pit with its various steam valves and connecting piping. Valve MSS-25, an 8-in. valve, is located at the bottom of the pit. The failed 6-in. valve was located at the top of the pit where it branched from the upper portion of the 8-in. line at the 8- by 8- by 6-in. tee and was then ``blanked off`` with a blind flange. The purpose of this technical evaluation was to determine the cause of the accident that led to the failure of the 6-in. valve. The probable cause for the 6-in. valve failure was determined by visual, nondestructive, and destructive examination of the failed valve and by metallurgical analysis of the fractured region of the valve. The cause of the accident was ultimately identified by correlating the observed failure mode to the most probable physical phenomenon. Thermal-hydraulic analyses, component stress analyses, and tests were performed to verify that the probable physical phenomenon could be reasonably expected to produce the failure in the valve that was observed.

  4. Study on the Accidental Rupture of Hot Leg or Surge Line in SBO Accident

    SciTech Connect (OSTI)

    Kun Zhang; Xuewu Cao [Shanghai Jiaotong University, Shanghai (China)

    2006-07-01

    The postulated total station blackout accident (SBO) of PWR NPP with 600 MWe in China is analyzed as the base case using SCDAP/RELAP5 code. Then the hot leg or surge line are assumed to rupture before the lower head of Reactor Pressure Vessel (RPV) ruptures, and the progressions are analyzed in detail comparing with the base case. The results show that the accidental rupture of hot leg or surge line will greatly influence the progression of accident. The probability of hot leg or surge line rupture in intentional depressurization is also studied in this paper, which provides a suggestion to the development of Severe Accident Management Guidelines (SAMG). (authors)

  5. Modeling of coupled thermodynamic and geomechanical performance of underground compressed air energy storage (CAES) in lined rock caverns

    E-Print Network [OSTI]

    Rutqvist, J.

    2013-01-01

    compressed air energy storage (CAES) in lined rock cavernsCompressed Air Energy Storage (CAES) in Lined Rock Cavernscompressed air energy storage (CAES) in concrete-lined rock

  6. Farm Fuel Safety Accidents in the handling, use and storage of gasoline, gasohol, diesel fuel, LP-gas and

    E-Print Network [OSTI]

    Tullos, Desiree

    112 Farm Fuel Safety Accidents in the handling, use and storage of gasoline, gasohol, diesel fuel and by keeping fuel storage facilities in top condition. Flammable Liquids and Gases Gasoline, diesel fuel, LP, deterioration or damage. Never store fuel in food or drink containers. When transferring farm fuels, bond

  7. TITAN code development for application to a PWR steam line break accident : final report 1983-1984

    E-Print Network [OSTI]

    Tsai, Chon-Kwo

    1984-01-01

    Modification of the TITAN computer code which enables it to be applied to a PWR steam line break accident has been accomplished. The code now has the capability of simulating an asymmetric inlet coolant temperature transient ...

  8. Characterizing excavation damaged zone and stability of pressurized lined rock caverns for underground compressed air energy storage

    E-Print Network [OSTI]

    Kim, H.M.

    2014-01-01

    Compressed Air Energy Storage Hyung-Mok Kim 1,4 , Jonnyof compressed air energy storage (CAES) in lined rockLRC); Compressed air energy storage (CAES); TOUGH-FLAC

  9. Type A Accident Investigation Report on the June 25, 1997, Contractor Inspector Fatality on the Satsop-Aberdeen #2 & #3 230 kV Line

    Broader source: Energy.gov [DOE]

    On June 27, 1997, I established a Type-A Accident Investigation Board to investigate the June 25, 1997 fatal contractor accident which occurred on BPA?s Satsop-Aberdeen #2 and #3 230-kV transmission lines right-of-way.

  10. Analysis of accident sequences and source terms at treatment and storage facilities for waste generated by US Department of Energy waste management operations

    SciTech Connect (OSTI)

    Mueller, C.; Nabelssi, B.; Roglans-Ribas, J.; Folga, S.; Policastro, A.; Freeman, W.; Jackson, R.; Mishima, J.; Turner, S.

    1996-12-01

    This report documents the methodology, computational framework, and results of facility accident analyses performed for the US Department of Energy (DOE) Waste Management Programmatic Environmental Impact Statement (WM PEIS). The accident sequences potentially important to human health risk are specified, their frequencies assessed, and the resultant radiological and chemical source terms evaluated. A personal-computer-based computational framework and database have been developed that provide these results as input to the WM PEIS for the calculation of human health risk impacts. The WM PEIS addresses management of five waste streams in the DOE complex: low-level waste (LLW), hazardous waste (HW), high-level waste (HLW), low-level mixed waste (LLMW), and transuranic waste (TRUW). Currently projected waste generation rates, storage inventories, and treatment process throughputs have been calculated for each of the waste streams. This report summarizes the accident analyses and aggregates the key results for each of the waste streams. Source terms are estimated, and results are presented for each of the major DOE sites and facilities by WM PEIS alternative for each waste stream. Key assumptions in the development of the source terms are identified. The appendices identify the potential atmospheric release of each toxic chemical or radionuclide for each accident scenario studied. They also discuss specific accident analysis data and guidance used or consulted in this report.

  11. Commercial potential of natural gas storage in lined rock caverns (LRC)

    SciTech Connect (OSTI)

    1999-11-01

    The geologic conditions in many regions of the United States will not permit the development of economical high-deliverability gas storage in salt caverns. These regions include the entire Eastern Seaboard; several northern states, notably Minnesota and Wisconsin; many of the Rocky Mountain States; and most of the Pacific Northwest. In late 1997, the United States Department of Energy (USDOE) Federal Energy Technology Center engaged Sofregaz US to investigate the commercialization potential of natural gas storage in Lined Rock Caverns (LRC). Sofregaz US teamed with Gaz de France and Sydkraft, who had formed a consortium, called LRC, to perform the study for the USDOE. Underground storage of natural gas is generally achieved in depleted oil and gas fields, aquifers, and solution-mined salt caverns. These storage technologies require specific geologic conditions. Unlined rock caverns have been used for decades to store hydrocarbons - mostly liquids such as crude oil, butane, and propane. The maximum operating pressure in unlined rock caverns is limited, since the host rock is never entirely impervious. The LRC technology allows a significant increase in the maximum operating pressure over the unlined storage cavern concept, since the gas in storage is completely contained with an impervious liner. The LRC technology has been under development in Sweden by Sydkraft since 1987. The development process has included extensive technical studies, laboratory testing, field tests, and most recently includes a storage facility being constructed in southern Sweden (Skallen). The LRC development effort has shown that the concept is technically and economically viable. The Skallen storage facility will have a rock cover of 115 meters (375 feet), a storage volume of 40,000 cubic meters (250,000 petroleum barrels), and a maximum operating pressure of 20 MPa (2,900 psi). There is a potential for commercialization of the LRC technology in the United States. Two regions were studied in some detail - the Northeast and the Southeast. The investment cost for an LRC facility in the Northeast is approximately $182 million and $343 million for a 2.6-billion cubic foot (bcf) working gas facility and a 5.2-bcf working gas storage facility, respectively. The relatively high investment cost is a strong function of the cost of labor in the Northeast. The labor union-related rules and requirements in the Northeast result in much higher underground construction costs than might result in Sweden, for example. The LRC technology gas storage service is compared to other alternative technologies. The LRC technology gas storage service was found to be competitive with other alternative technologies for a variety of market scenarios.

  12. Accident Investigation of the June 17, 2012, Construction Accident...

    Energy Savers [EERE]

    June 17, 2012, Construction Accident - Structural Steel Collapse at The Over pack Storage Expansion 2 at the Naval Reactors Facility at the Idaho National Laboratory, Idaho Falls,...

  13. Allocation of inventory to a variable, time-phased, on-line storage system under known demand 

    E-Print Network [OSTI]

    White, Charles Wesley

    1968-01-01

    ALLOCATION OF INVENTORY TO A VARIABLE, TIME-PHASED, ON-LINE STORAGE SYSTEM UNDER KNOWN DEMAND A Thesis By CHARLES WESLEY WHITE Submitted to the Graduate College of the Texas ASM University in partial fulfillment of the requirements... for the degree of MASTER OF SCIENCE January, 1968 Major Subject: Industrial Engineering ALLOCATION OF INVENTORY TO A VARIABLE ~ T IME PHASED ~ ON L INE STORAGE SYSTEM UNDER KNOWN DEMAND A Thesis By CHARLES WESLEY WHITE Approved as to style...

  14. Modeling of coupled thermodynamic and geomechanical performance of underground compressed air energy storage (CAES) in lined rock caverns

    SciTech Connect (OSTI)

    Rutqvist, J.; Kim, H. -M.; Ryu, D. -W.; Synn, J. -H.; Song, W. -K.

    2012-02-01

    We applied coupled nonisothermal, multiphase fluid flow and geomechanical numerical modeling to study the coupled thermodynamic and geomechanical performance of underground compressed air energy storage (CAES) in concrete-lined rock caverns. The paper focuses on CAES in lined caverns at relatively shallow depth (e.g., 100 m depth) in which a typical CAES operational pressure of 5 to 8 MPa is significantly higher than both ambient fluid pressure and in situ stress. We simulated a storage operation that included cyclic compression and decompression of air in the cavern, and investigated how pressure, temperature and stress evolve over several months of operation. We analyzed two different lining options, both with a 50 cm thick low permeability concrete lining, but in one case with an internal synthetic seal such as steel or rubber. For our simulated CAES system, the thermodynamic analysis showed that 96.7% of the energy injected during compression could be recovered during subsequent decompression, while 3.3% of the energy was lost by heat conduction to the surrounding media. Our geomechanical analysis showed that tensile effective stresses as high as 8 MPa could develop in the lining as a result of the air pressure exerted on the inner surface of the lining, whereas thermal stresses were relatively smaller and compressive. With the option of an internal synthetic seal, the maximum effective tensile stress was reduced from 8 to 5 MPa, but was still in substantial tension. We performed one simulation in which the tensile tangential stresses resulted in radial cracks and air leakage though the lining. This air leakage, however, was minor (about 0.16% of the air mass loss from one daily compression) in terms of CAES operational efficiency, and did not significantly impact the overall energy balance of the system. However, despite being minor in terms of energy balance, the air leakage resulted in a distinct pressure increase in the surrounding rock that could be quickly detected using pressure monitoring outside the concrete lining.

  15. Type B Accident Investigation Board Report on the May 7, 1997, Worker Injury at the Hanford Site Canister Storage Building Construction Site, Richland, Washington

    Broader source: Energy.gov [DOE]

    This report is an independent product of the Type B Accident Investigation Board appointed by Michael S. Cowan, Chief Program Officer, Western Area Power Administration.

  16. Accident management for severe accidents

    SciTech Connect (OSTI)

    Bari, R.A.; Pratt, W.T.; Lehner, J.; Leonard, M.; Disalvo, R.; Sheron, B.

    1988-01-01

    The management of severe accidents in light water reactors is receiving much attention in several countries. The reduction of risk by measures and/or actions that would affect the behavior of a severe accident is discussed. The research program that is being conducted by the US Nuclear Regulatory Commission focuses on both in-vessel accident management and containment and release accident management. The key issues and approaches taken in this program are summarized. 6 refs.

  17. Modeling of coupled thermodynamic and geomechanical performance of underground compressed air energy storage (CAES) in lined rock caverns

    E-Print Network [OSTI]

    Rutqvist, J.

    2013-01-01

    Williams, Compressed air energy storage: Theory, resources,for the compressed air energy storage technology by thefor compressed air energy storage power generation, Japan

  18. Modeling of coupled thermodynamic and geomechanical performance of underground compressed air energy storage (CAES) in lined rock caverns

    E-Print Network [OSTI]

    Rutqvist, J.

    2013-01-01

    abandonment Underground gas storage: Worldwide ExperiencesCritical pressure for gas storage in unlined rock caverns.for the Brooklyn Union gas storage cavern at JFK Airport,

  19. Type B Accident Investigation Board Report on the November 17, 1997, Chiller Line Rupture at Technical Area 35, Building 27, Los Alamos National Laboratory

    Broader source: Energy.gov [DOE]

    This report is a product of an accident investigation board appointed by Bruce G. Twining, Manager, Albuquerque Operations Office, Department of Energy.

  20. Type B Accident Investigation Board Report on the September 1, 1999, Plutonium Intakes at the Savannah River Site FB-Line

    Office of Energy Efficiency and Renewable Energy (EERE)

    This report is an independent product of the Type B Accident Investigation Board appointed by Greg Rudy, Manager, Savannah River Operations Office, U.S. Department of Energy.

  1. Type A Accident Investigation Board Report on the February 20, 1996, Fall Fatality at the Radioactive Waste Management Complex Transuranic Storage Area- Retrieval Enclosure, Idaho National Engineering Laboratory

    Broader source: Energy.gov [DOE]

    This report is an independent product of the Type A Accident Investigation Board appointed by Tara O’Toole, M.D., M.P.H., Assistant Secretary for Environment, Safety and Health (EH-1).

  2. Accident Investigations

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1996-04-26

    To prescribe requirements for conducting investigations of certain accidents occurring at Department of Energy (DOE) operations and sites; to improve the environment, safety and health for DOE, contractors, and the public; and to prevent the recurrence of such accidents. Chg 2, 4-26-96

  3. Accident Investigations

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1995-10-26

    To prescribe requirements for conducting investigations of certain accidents occurring at Department of Energy (DOE) operations and sites; to improve the environment , safety and health for DOE, contractors, and the public; and to prevent the recurrence of such accidents. Chg 1, 10-26-95. Cancels parts of DOE 5484.1

  4. Type A Accident Investigation Board Report on the February 20...

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

    February 20, 1996, Fall Fatality at the Radioactive Waste Management Complex Transuranic Storage Area - Retrieval Enclosure, Idaho National Engineering Laboratory Type A Accident...

  5. Accident Investigations

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2011-03-04

    This Order prescribes organizational responsibilities, authorities, and requirements for conducting investigations of certain accidents occurring at DOE sites, facilities, areas, operations, and activities. Supersedes DOE O 225.1A. Cancels DOE G 225.1A-1.

  6. Type B Accident Investigation Board Report on the July 25, 1997, Contract Brush Cutter Injury on the Ashe-Marion #2 500 kV Line

    Broader source: Energy.gov [DOE]

    On July 25, 1997, at 1205 hours, a contract hand brush cutter was seriously injured when he felled a tree close to a Bonneville Power Administration energized transmission power line, located within a BPA transmission-line corridor.

  7. Exploring the concept of compressed air energy storage (CAES) in lined rock caverns at shallow depth: A modeling study of air tightness and energy balance

    E-Print Network [OSTI]

    Kim, H.-M.

    2012-01-01

    Progress in electrical energy storage system: a criticalcurrent and future energy storage technologies for electricwind- diesel-compressed air energy storage system for remote

  8. Modeling of coupled thermodynamic and geomechanical performance of underground compressed air energy storage (CAES) in lined rock caverns

    E-Print Network [OSTI]

    Rutqvist, J.

    2013-01-01

    initial (intact) concrete permeability, A is estimated froma 50 cm thick low permeability concrete lining, but in onefor relying on low-permeability concrete as a primary seal,

  9. Accident information needs

    SciTech Connect (OSTI)

    Hanson, D.J.; Arcieri, W.C.; Ward, L.W.

    1992-12-31

    A Five-step methodology has been developed to evaluate information needs for nuclear power plants under accident conditions and the availability of plant instrumentation during severe accidents. Step 1 examines the credible accidents and their relationships to plant safety functions. Step 2 determines the information personnel involved in accident management will need to understand plant behavior. Step 3 determines the capability of the instrumentation to function properly under severe accident conditions. Step 4 determines the conditions expected during the identified severe accidents. Step 5 compares the instrument capabilities and the severe accident conditions to evaluate the availability of the instrumentation to supply needed plant information.

  10. Accident information needs

    SciTech Connect (OSTI)

    Hanson, D.J.; Arcieri, W.C.; Ward, L.W.

    1992-01-01

    A Five-step methodology has been developed to evaluate information needs for nuclear power plants under accident conditions and the availability of plant instrumentation during severe accidents. Step 1 examines the credible accidents and their relationships to plant safety functions. Step 2 determines the information personnel involved in accident management will need to understand plant behavior. Step 3 determines the capability of the instrumentation to function properly under severe accident conditions. Step 4 determines the conditions expected during the identified severe accidents. Step 5 compares the instrument capabilities and the severe accident conditions to evaluate the availability of the instrumentation to supply needed plant information.

  11. Fracture Optimization eXpert (FOX) -How Computational Intelligence Helps the Bottom-Line in Gas Storage; A Case Study

    E-Print Network [OSTI]

    Mohaghegh, Shahab

    SPE 37341 Fracture Optimization eXpert (FOX) - How Computational Intelligence Helps the Bottom, conventional or unconven- tional, is evaluated by its contribution to the bottom-line. Fracture Optimization e

  12. FIELD LINES TWISTING IN A NOISY CORONA: IMPLICATIONS FOR ENERGY STORAGE AND RELEASE, AND INITIATION OF SOLAR ERUPTIONS

    SciTech Connect (OSTI)

    Rappazzo, A. F. [Bartol Research Institute, Department of Physics and Astronomy, University of Delaware, DE 19716 (United States); Velli, M. [Jet Propulsion Laboratory, California Institute of Technology, Pasadena, CA 91109 (United States); Einaudi, G., E-mail: rappazzo@udel.edu [Berkeley Research Associates, Inc., 6537 Mid Cities Avenue, Beltsville, MD 20705 (United States)

    2013-07-10

    We present simulations modeling closed regions of the solar corona threaded by a strong magnetic field where localized photospheric vortical motions twist the coronal field lines. The linear and nonlinear dynamics are investigated in the reduced magnetohydrodynamic regime in Cartesian geometry. Initially the magnetic field lines get twisted and the system becomes unstable to the internal kink mode, confirming and extending previous results. As typical in this kind of investigations, where initial conditions implement smooth fields and flux-tubes, we have neglected fluctuations and the fields are laminar until the instability sets in. However, previous investigations indicate that fluctuations, excited by photospheric motions and coronal dynamics, are naturally present at all scales in the coronal fields. Thus, in order to understand the effect of a photospheric vortex on a more realistic corona, we continue the simulations after kink instability sets in, when turbulent fluctuations have already developed in the corona. In the nonlinear stage the system never returns to the simple initial state with ordered twisted field lines, and kink instability does not occur again. Nevertheless, field lines get twisted, although in a disordered way, and energy accumulates at large scales through an inverse cascade. This energy can subsequently be released in micro-flares or larger flares, when interaction with neighboring structures occurs or via other mechanisms. The impact on coronal dynamics and coronal mass ejections initiation is discussed.

  13. Type A Accident Investigation Report – Western Area Power Administration Investigation of the June 7, 2004, Construction Contractor Electrical Accident at Double-Circuit Structure 38/1, Watertown-Granite Falls 230-kV Transmission Line East of Watertown, S

    Broader source: Energy.gov [DOE]

    This report is an independent product of the Type A Accident Investigation board appointed by Timothy J. Meeks, Chief Operating Officer, Western Area Power Administration.

  14. Interpreting Accident Statistics

    E-Print Network [OSTI]

    Ferreira, Joseph Jr.

    Accident statistics have often been used to support the argument that an abnormally small proportion of drivers account for a large proportion of the accidents. This paper compares statistics developed from six-year data ...

  15. Field lines twisting in a noisy corona: implications for energy storage and release, and initiation of solar eruptions

    E-Print Network [OSTI]

    Rappazzo, A F; Einaudi, G

    2013-01-01

    We present simulations modeling closed regions of the solar corona threaded by a strong magnetic field where localized photospheric vortical motions twist the coronal field lines. The linear and nonlinear dynamics are investigated in the reduced magnetohydrodynamic regime in Cartesian geometry. Initially the magnetic field lines get twisted and the system becomes unstable to the internal kink mode, confirming and extending previous results. As typical in this kind of investigations, where initial conditions implement smooth fields and flux-tubes, we have neglected fluctuations and the fields are laminar until the instability sets in. But previous investigations indicate that fluctuations, excited by photospheric motions and coronal dynamics, are naturally present at all scales in the coronal fields. Thus, in order to understand the effect of a photospheric vortex on a more realistic corona, we continue the simulations after kink instability sets in, when turbulent fluctuations have already developed in the co...

  16. Accident Investigation of the July 30, 2013, Electrical Fatality...

    Energy Savers [EERE]

    July 30, 2013, Electrical Fatality on the Bandon-Rogue No. 1 115kV Line at the Bonneville Power Administration Accident Investigation of the July 30, 2013, Electrical Fatality on...

  17. Data Storage Data Storage

    E-Print Network [OSTI]

    Jiang, Anxiao "Andrew"

    I Data Storage #12;#12;Data Storage Edited by Prof. Florin Balasa In-Tech intechweb.org #12 Jakobovic Cover designed by Dino Smrekar Data Storage, Edited by Prof. Florin Balasa p. cm. ISBN 978-953-307-063-6 #12;V Preface Many different forms of storage, based on various natural phenomena, has been invented

  18. Exploring the concept of compressed air energy storage (CAES) in lined rock caverns at shallow depth: A modeling study of air tightness and energy balance

    E-Print Network [OSTI]

    Kim, H.-M.

    2012-01-01

    3.3 Case of Leaky Concrete Lining and Permeable Rock In thiswith a comparatively permeable concrete lining. 3.4 Leakagesystem with relatively permeable concrete lining and rock,

  19. Management of severe accidents

    SciTech Connect (OSTI)

    Jankowski, M.W.

    1988-01-01

    The definition and the multidimensionality aspects of accident management have been reviewed. The suggested elements in the development of a programme for severe accident management have been identified and discussed. The strategies concentrate on the two tiered approaches. Operative management utilizes the plant's equipment and operators capabilities. The recovery management concentrates on preserving the containment, or delaying its failure, inhibiting the release, and on strategies once there has been a release. The inspiration for this paper was an excellent overview report on perspectives on managing severe accidents in commercial nuclear power plants and extending plant operating procedures into the severe accident regime; and by the most recent publication of the International Nuclear Safety Advisory Group (INSAG) considering the question of risk reduction and source term reduction through accident prevention, management and mitigation. The latter document concludes that active development of accident management measures by plant personnel can lead to very large reductions in source terms and risk, and goes further in considering and formulating the key issue: The most fruitful path to follow in reducing risk even further is through the planning of accident management.

  20. Accident resistant transport container

    DOE Patents [OSTI]

    Andersen, John A. (Albuquerque, NM); Cole, James K. (Albuquerque, NM)

    1980-01-01

    The invention relates to a container for the safe air transport of plutonium having several intermediate wood layers and a load spreader intermediate an inner container and an outer shell for mitigation of shock during a hypothetical accident.

  1. Accident motivates scholarship recipient

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

    accident, college wasn't on my mind. I was all about sports," said Leyba, who played football, basketball, and ran track at the small Northern New Mexico school. "I had no idea...

  2. Accident management information needs

    SciTech Connect (OSTI)

    Hanson, D.J.; Ward, L.W.; Nelson, W.R.; Meyer, O.R. (EG and G Idaho, Inc., Idaho Falls, ID (USA))

    1990-04-01

    In support of the US Nuclear Regulatory Commission (NRC) Accident Management Research Program, a methodology has been developed for identifying the plant information needs necessary for personnel involved in the management of an accident to diagnose that an accident is in progress, select and implement strategies to prevent or mitigate the accident, and monitor the effectiveness of these strategies. This report describes the methodology and presents an application of this methodology to a Pressurized Water Reactor (PWR) with a large dry containment. A risk-important severe accident sequence for a PWR is used to examine the capability of the existing measurements to supply the necessary information. The method includes an assessment of the effects of the sequence on the measurement availability including the effects of environmental conditions. The information needs and capabilities identified using this approach are also intended to form the basis for more comprehensive information needs assessment performed during the analyses and development of specific strategies for use in accident management prevention and mitigation. 3 refs., 16 figs., 7 tabs.

  3. Primer on lead-acid storage batteries

    SciTech Connect (OSTI)

    1995-09-01

    This handbook was developed to help DOE facility contractors prevent accidents caused during operation and maintenance of lead-acid storage batteries. Major types of lead-acid storage batteries are discussed as well as their operation, application, selection, maintenance, and disposal (storage, transportation, as well). Safety hazards and precautions are discussed in the section on battery maintenance. References to industry standards are included for selection, maintenance, and disposal.

  4. Accident motivates scholarship recipient

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room News Publications Traditional Knowledge KiosksAbout UsAboutWeb PoliciesAccidentAccident

  5. Calculation notes in support of TWRS FSAR spray leak accident analysis

    SciTech Connect (OSTI)

    Hall, B.W.

    1996-09-25

    This document contains the detailed calculations that support the spray leak accident analysis in the Tank Waste Remediation System (TWRS) Final Safety Analysis Report (FSAR). The consequence analyses in this document form the basis for the selection of controls to mitigate or prevent spray leaks throughout TWRS. Pressurized spray leaks can occur due to a breach in containment barriers along transfer routes, during waste transfers. Spray leaks are of particular safety concern because, depending on leak dimensions, and waste pressure, they can be relatively efficient generators of dispersible sized aerosols that can transport downwind to onsite and offsite receptors. Waste is transferred between storage tanks and between processing facilities and storage tanks in TWRS through a system of buried transfer lines. Pumps for transferring waste and jumpers and valves for rerouting waste are located inside below grade pits and structures that are normally covered. Pressurized spray leaks can emanate to the atmosphere due to breaches in waste transfer associated equipment inside these structures should the structures be uncovered at the time of the leak. Pressurized spray leaks can develop through holes or cracks in transfer piping, valve bodies or pump casings caused by such mechanisms as corrosion, erosion, thermal stress, or water hammer. Leaks through degraded valve packing, jumper gaskets, or pump seals can also result in pressurized spray releases. Mechanisms that can degrade seals, packing and gaskets include aging, radiation hardening, thermal stress, etc. An1782other common cause for spray leaks inside transfer enclosures are misaligned jumpers caused by human error. A spray leak inside a DST valve pit during a transfer of aging waste was selected as the bounding, representative accident for detailed analysis. Sections 2 through 5 below develop this representative accident using the DOE- STD-3009 format. Sections 2 describes the unmitigated and mitigated accident scenarios evaluated to determine the need for safety class SSCs or TSR controls. Section 3 develops the source terms associated with the unmitigated and mitigated accident scenarios. Section 4 estimates the radiological and toxicological consequences for the unmitigated and mitigated scenarios. Section 5 compares the radiological and toxicological consequences against the TWRS evaluation guidelines. Section 6 extrapolates from the representative accident case to other represented spray leak sites to assess the conservatism in using the representative case to define controls for other postulated spray leak sites throughout TWRS. Section 7 discusses the sensitivities of the consequence analyses to the key parameters and assumptions used in the analyses. Conclusions are drawn in Section 8. The analyses herein pertain to spray leaks initiated due to internal mechanisms (e.g., corrosion, erosion, thermal stress, etc). External initiators of spray leaks (e.g., excavation accidents), and natural phenomena initiators (e.g., seismic events) are to be covered in separate accident analyses.

  6. Structural assessment of accident loads

    SciTech Connect (OSTI)

    Wagenblast, G.R., Westinghouse Hanford

    1996-05-28

    Structural assessments were made for specific accident loads for specific catch, receiver, and storage tanks. The evaluation herein represents level-of-effort order-of-magnitude estimates of limiting loads that would lead to collapse or rupture of the tank and unmitigated loss of confinement for the waste. Structural capacities were established using failure criteria. Compliance with codes such as ACI, ASCE, ASME, RCRA, UBC, WAC, and DOE Orders was `NOT` maintained. Normal code practice is to prevent failure with margins consistent with expected variations in loads and strengths and confidence in analysis techniques. The evaluation herein represent estimates of code limits without code load factors or code strength reduction factors, and loading beyond such a limit is considered as an onset of some failure mode. The exact nature of the failure mode and its relation to a safe condition is a judgment of the analyst. Consequently, these `RESULTS SHALL NOT BE USED TO ESTABLISH OPERATING OR SAFETY LOAD LIMITS FOR THESE TANKS`.

  7. Hanford waste tank bump accident analysis

    SciTech Connect (OSTI)

    MALINOVIC, B.

    2003-03-21

    This report provides a new evaluation of the Hanford tank bump accident analysis (HNF-SD-Wh4-SAR-067 2001). The purpose of the new evaluation is to consider new information and to support new recommendations for final safety controls. This evaluation considers historical data, industrial failure modes, plausible accident scenarios, and system responses. A tank bump is a postulated event in which gases, consisting mostly of water vapor, are suddenly emitted from the waste and cause tank headspace pressurization. A tank bump is distinguished from a gas release event in two respects: First, the physical mechanism for release involves vaporization of locally superheated liquid, and second, gases emitted to the head space are not flammable. For this reason, a tank bump is often called a steam bump. In this report, even though non-condensible gases may be considered in bump models, flammability and combustion of emitted gases are not. The analysis scope is safe storage of waste in its current configuration in single-shell tanks (SSTs) and double-shell tanks (DSTs). The analysis considers physical mechanisms for tank bump to formulate criteria for bump potential, application of the criteria to the tanks, and accident analysis of bump scenarios. The result of consequence analysis is the mass of waste released from tanks for specific scenarios where bumps are credible; conversion to health consequences is performed elsewhere using standard Hanford methods (Cowley et al. 2000). The analysis forms a baseline for future extension to consider waste retrieval.

  8. Exploring the concept of compressed air energy storage (CAES) in lined rock caverns at shallow depth: A modeling study of air tightness and energy balance

    E-Print Network [OSTI]

    Kim, H.-M.

    2012-01-01

    Calculated time integrated energy balance term in the 5 thCalculated time integrated energy balance term in the 5 thcurve. Figure 18. Energy balance terms for the tight lining

  9. Exploring the concept of compressed air energy storage (CAES) in lined rock caverns at shallow depth: A modeling study of air tightness and energy balance

    E-Print Network [OSTI]

    Kim, H.-M.

    2012-01-01

    and R. Scharf, Huntroft CAES: More than 20 years ofbase case for modeling of CAES in a lined rock cavern. TableFigure 2. Components of a CAES system (modified from http://

  10. Exploring the concept of compressed air energy storage (CAES) in lined rock caverns at shallow depth: A modeling study of air tightness and energy balance

    E-Print Network [OSTI]

    Kim, H.-M.

    2012-01-01

    system, i.e. , for a concrete permeability off less than 1×of a relatively low concrete permeability. Most temperatureindicated that a concrete lining with a permeability of less

  11. Electrical shock accident investigation

    SciTech Connect (OSTI)

    Not Available

    1994-09-30

    This report documents results of the accident investigation of an electrical shock received by two subcontractor employees on May 13, 1994, at the Pinellas Plant. The direct cause of the electrical shock was worker contact with a cut ``hot`` wire and a grounded panelboard (PPA) enclosure. Workers presumed that all wires in the enclosure were dead at the time of the accident and did not perform thorough Lockout/Tagout (LO/TO). Three contributing causes were identified. First, lack of guidance in the drawing for the modification performed in 1987 allowed the PPA panel to be used as a junction box. The second contributing cause is that Environmental, Safety and Health (ES&H) procedures do not address multiple electrical sources in an enclosure. Finally, the workers did not consider the possibility of multiple electrical sources. The root cause of the electrical shock was the inadequacy of administrative controls, including construction requirement and LO/TO requirements, and subcontractor awareness regarding multiple electrical sources. Recommendations to prevent further reoccurrence of this type of accident include revision of ES&H Standard 2.00, Electrical Safety Program Manual, to document requirements for multiple electrical sources in a single enclosure to specify a thorough visual inspection as part of the voltage check process. In addition, the formality of LO/TO awareness training for subcontractor electricians should be increased.

  12. Sandia Energy - Severe Accident Modeling

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

    nuclear energy efforts by developing risk margins, creating risk assessments, sequencing nuclear reactor accident progression, and performing reactor consequence modeling. Severe...

  13. Industry program needed for nuclear accident management

    SciTech Connect (OSTI)

    Klopp, G.T

    1989-05-01

    This paper addresses the need for a management program for nuclear power accidents. According to the author, the tools and technology for severe accident management exist. The need for a clear, realistic definition of nuclear accident program requirements is discussed.

  14. First Responders and Criticality Accidents

    SciTech Connect (OSTI)

    Valerie L. Putman; Douglas M. Minnema

    2005-11-01

    Nuclear criticality accident descriptions typically include, but do not focus on, information useful to first responders. We studied these accidents, noting characteristics to help (1) first responders prepare for such an event and (2) emergency drill planners develop appropriate simulations for training. We also provide recommendations to help people prepare for such events in the future.

  15. Computerized Accident Incident Reporting System | Department...

    Office of Environmental Management (EM)

    Incident Reporting System Computerized Accident Incident Reporting System CAIRS Database The Computerized AccidentIncident Reporting System is a database used to collect and...

  16. Accident Tolerant Fuel Analysis

    SciTech Connect (OSTI)

    Curtis Smith; Heather Chichester; Jesse Johns; Melissa Teague; Michael Tonks; Robert Youngblood

    2014-09-01

    Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about light water reactor design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway research and development (R&D) is to support plant decisions for risk-informed margins management by improving economics and reliability, and sustaining safety, of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced “RISMC toolkit” that enables more accurate representation of NPP safety margin. In order to carry out the R&D needed for the Pathway, the Idaho National Laboratory is performing a series of case studies that will explore methods- and tools-development issues, in addition to being of current interest in their own right. One such study is a comparative analysis of safety margins of plants using different fuel cladding types: specifically, a comparison between current-technology Zircaloy cladding and a notional “accident-tolerant” (e.g., SiC-based) cladding. The present report begins the process of applying capabilities that are still under development to the problem of assessing new fuel designs. The approach and lessons learned from this case study will be included in future Technical Basis Guides produced by the RISMC Pathway. These guides will be the mechanism for developing the specifications for RISMC tools and for defining how plant decision makers should propose and evaluate margin recovery strategies.

  17. Accident tolerant fuel analysis

    SciTech Connect (OSTI)

    Smith, Curtis; Chichester, Heather; Johns, Jesse; Teague, Melissa; Tonks, Michael Idaho National Laboratory; Youngblood, Robert

    2014-09-01

    Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about light water reactor design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway research and development (R&D) is to support plant decisions for risk-informed margins management by improving economics and reliability, and sustaining safety, of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced ''RISMC toolkit'' that enables more accurate representation of NPP safety margin. In order to carry out the R&D needed for the Pathway, the Idaho National Laboratory is performing a series of case studies that will explore methods- and tools-development issues, in addition to being of current interest in their own right. One such study is a comparative analysis of safety margins of plants using different fuel cladding types: specifically, a comparison between current-technology Zircaloy cladding and a notional ''accident-tolerant'' (e.g., SiC-based) cladding. The present report begins the process of applying capabilities that are still under development to the problem of assessing new fuel designs. The approach and lessons learned from this case study will be included in future Technical Basis Guides produced by the RISMC Pathway. These guides will be the mechanism for developing the specifications for RISMC tools and for defining how plant decision makers should propose and evaluate margin recovery strategies.

  18. ACCIDENT ANALYSES & CONTROL OPTIONS IN SUPPORT OF THE SLUDGE WATER SYSTEM SAFETY ANALYSIS

    SciTech Connect (OSTI)

    WILLIAMS, J.C.

    2003-11-15

    This report documents the accident analyses and nuclear safety control options for use in Revision 7 of HNF-SD-WM-SAR-062, ''K Basins Safety Analysis Report'' and Revision 4 of HNF-SD-SNF-TSR-001, ''Technical Safety Requirements - 100 KE and 100 KW Fuel Storage Basins''. These documents will define the authorization basis for Sludge Water System (SWS) operations. This report follows the guidance of DOE-STD-3009-94, ''Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports'', for calculating onsite and offsite consequences. The accident analysis summary is shown in Table ES-1 below. While this document describes and discusses potential control options to either mitigate or prevent the accidents discussed herein, it should be made clear that the final control selection for any accident is determined and presented in HNF-SD-WM-SAR-062.

  19. Energy Storage

    ScienceCinema (OSTI)

    Paranthaman, Parans

    2014-06-23

    ORNL Distinguished Scientist Parans Paranthaman is discovering new materials with potential for greatly increasing batteries' energy storage capacity and bring manufacturing back to the US.

  20. Energy Storage

    SciTech Connect (OSTI)

    Paranthaman, Parans

    2014-06-03

    ORNL Distinguished Scientist Parans Paranthaman is discovering new materials with potential for greatly increasing batteries' energy storage capacity and bring manufacturing back to the US.

  1. Environment/Health/Safety (EHS): Monthly Accident Statistics

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

    Personal Protective Equipment (PPE) Injury Review & Analysis Worker Safety and Health Program: PUB-3851 Monthly Accident Statistics Latest Accident Statistics Accident...

  2. Terrestrial Water Storage

    E-Print Network [OSTI]

    Rodell, M; Chambers, D P; Famiglietti, Jay

    2013-01-01

    T. E. Reilly, 2002: Flow and storage in groundwater systems.storage ..2013: Global ocean storage of anthropogenic carbon.

  3. Stasis: Flexible Transactional Storage

    E-Print Network [OSTI]

    Sears, Russell C.

    2009-01-01

    storage . . . . . . . . . . . . . . . . . . . . . .example system based on log-structured storage 10.1 SystemA storage bottleneck. . . . . . . . . . . . . . . .

  4. Analysis of accidents during flashing operations 

    E-Print Network [OSTI]

    Obermeyer, Michael Edward

    1993-01-01

    . In this thesis, the relative impacts of flashing signal operation versus regular signal operation were evaluated in several cities and towns in the State of Texas. Analysis were conducted to determine whether an increase in accidents and accident severity...

  5. Porous media compressed air energy storage (PM-CAES): Theory and simulation of the coupled wellbore-reservoir system

    E-Print Network [OSTI]

    Oldenburg, C.M.

    2014-01-01

    compressed air energy storage (CAES), Energy, 32, 120-127.compressed air energy storage (CAES) in lined rock cavernsflow within aquifer reservoirs of CAES plants, Trans. Porous

  6. Specific topics in severe accident management

    SciTech Connect (OSTI)

    Meyer, J.F.; Chung, D.T.; Panciera, V.W.; Traver, L.E.; Humphries, D.S. (SCIENTECH, Inc., Rockville, MD (USA))

    1991-05-01

    This report examines five topical areas of concern to severe accident management. These areas are as follows: Human Factors, Accident Management During Shutdown, Information Needs, Long-term Implications, and Uncertainties. The objective of this report is to assist the NRC in performing its research function and to provide guidance to the industry on accident management strategies, as well as to accident management programs in general. 47 refs., 4 figs., 5 tabs.

  7. UNIVERSITY OF TRENTO ACCIDENT INSURANCE

    E-Print Network [OSTI]

    or freezing; · electrocution; · sunstrokes, hot or cold strokes; · lesions caused by muscular efforts. Sanitary transportation expenses (always included) The Company refunds, up to a liability limit of 500 for the transport from the place of the accident to an equipped Healthcare Institute, the transport among Health

  8. Hydrogen Storage

    Fuel Cell Technologies Publication and Product Library (EERE)

    This 2-page fact sheet provides a brief introduction to hydrogen storage technologies. Intended for a non-technical audience, it explains the different ways in which hydrogen can be stored, as well a

  9. Safety Issues Chemical Storage

    E-Print Network [OSTI]

    Cohen, Robert E.

    Safety Issues · Chemical Storage ·Store in compatible containers that are in good condition to store separately. #12;Safety Issues · Flammable liquid storage -Store bulk quantities in flammable storage cabinets -UL approved Flammable Storage Refrigerators are required for cold storage · Provide

  10. Cofrentes NPP activities on PSA and severe accident analysis

    SciTech Connect (OSTI)

    Suarez, J.; Borondo, L. [IBERDROLA, Madrid (Spain); Garcia, P.J. [UITESA, Madrid (Spain). Nuclear Dept.

    1996-07-01

    Cofrentes NPP (CNPP) has developed a Level 1 PSA with the following scope: analysis of internal events, with the reactor initially operating at power, internal and external flooding risk analysis; internal fire risk analysis; reliability analysis of the containment heat removal and containment isolation systems. Level 1 CNPP-PSA results reveal that total core damage frequency in CNPP is less than other similar BWR/6 plants. The CNPP-PSA related activities and applications being carried out currently are: adjusting of MAAP 3.0B, revision 10, on VAX and PC; acquisition of MAAP 4; development of Level1/Level2-PSA interface; seismic site categorization for the IPEEE; prioritization of motor operated valves related to GL-89/10, complementary analysis for exemption to some 10CFR50 App. J requirements; Q-List grading; reliability-centered maintenance; maintenance rule support; on-line maintenance support, off-line risk-monitor development, PSA applicability to the 10CFR50 App. R requirements, analysis of the frequency of mis-oriented fuel bundle event, etc. About severe accident management, CNPP, as part of the Spanish-BWROG, is currently analyzing the generic products of the US-BWROG AMG in order to generate their specific ones. Also, in this group BWR, the development of tools to simulate accident scenarios beyond core damage will be studied and a training process oriented to warrant the optimum use of new EOP/AMG in accident scenarios will be implemented.

  11. Accident management for indian pressurized heavy water reactors

    SciTech Connect (OSTI)

    Hajela, S.; Grover, R.; Ghadge, S.G.; Bajaj, S.S. [Directorate of Safety, Nuclear Power Corporation of India Limited Nabhikiya Urja Bhawan, Anushakti Nagar, Mumbai-400 094 (India)

    2006-07-01

    Indian nuclear power program as of now is mainly based on Pressurized Heavy Water Reactors (PHWRs). Operating Procedures for normal power operation and Emergency Operating Procedures for operational transients and accidents within design basis exist for all Indian PHWRs. In addition, on-site and off-site emergency response procedures are also available for these NPPs. The guidelines needed for severe accidents mitigation are now formally being documented for Indian PHWRs. Also, in line with International trend of having symptom based emergency handling, the work is in advanced stage for preparation of symptom-based emergency operating procedures. Following a plant upset condition; a number of alarms distributed in different information systems appear in the control room to aid operator to identify the nature of the event. After identifying the event, appropriate intervention in the form of event based emergency operating procedure is put into use by the operating staff. However, if the initiating event cannot be unambiguously identified or after the initial event some other failures take place, then the selected event based emergency operating procedure will not be optimal. In such a case, reactor safety is ensured by monitoring safety functions (depicted by selected plant parameters grouped together) throughout the event handling so that the barriers to radioactivity release namely, fuel and fuel cladding, primary heat transport system integrity and containment remain intact. Simultaneous monitoring of all these safety functions is proposed through status trees and this concept will be implemented through a computer-based system. For beyond design basis accidents, event sequences are identified which may lead to severe core damage. As part of this project, severe accident mitigation guidelines are being finalized for the selected event sequences. The paper brings out the details of work being carried out for Indian PHWRs for symptom based event handling and severe accident management. (authors)

  12. Accident analysis and DOE criteria

    SciTech Connect (OSTI)

    Graf, J.M.; Elder, J.C.

    1982-01-01

    In analyzing the radiological consequences of major accidents at DOE facilities one finds that many facilities fall so far below the limits of DOE Order 6430 that compliance is easily demonstrated by simple analysis. For those cases where the amount of radioactive material and the dispersive energy available are enough for accident consequences to approach the limits, the models and assumptions used become critical. In some cases the models themselves are the difference between meeting the criteria or not meeting them. Further, in one case, we found that not only did the selection of models determine compliance but the selection of applicable criteria from different chapters of Order 6430 also made the difference. DOE has recognized the problem of different criteria in different chapters applying to one facility, and has proceeded to make changes for the sake of consistency. We have proposed to outline the specific steps needed in an accident analysis and suggest appropriate models, parameters, and assumptions. As a result we feed DOE siting and design criteria will be more fairly and consistently applied.

  13. Energy Storage

    SciTech Connect (OSTI)

    Mukundan, Rangachary

    2014-09-30

    Energy storage technology is critical if the U.S. is to achieve more than 25% penetration of renewable electrical energy, given the intermittency of wind and solar. Energy density is a critical parameter in the economic viability of any energy storage system with liquid fuels being 10 to 100 times better than batteries. However, the economical conversion of electricity to fuel still presents significant technical challenges. This project addressed these challenges by focusing on a specific approach: efficient processes to convert electricity, water and nitrogen to ammonia. Ammonia has many attributes that make it the ideal energy storage compound. The feed stocks are plentiful, ammonia is easily liquefied and routinely stored in large volumes in cheap containers, and it has exceptional energy density for grid scale electrical energy storage. Ammonia can be oxidized efficiently in fuel cells or advanced Carnot cycle engines yielding water and nitrogen as end products. Because of the high energy density and low reactivity of ammonia, the capital cost for grid storage will be lower than any other storage application. This project developed the theoretical foundations of N2 catalysis on specific catalysts and provided for the first time experimental evidence for activation of Mo 2N based catalysts. Theory also revealed that the N atom adsorbed in the bridging position between two metal atoms is the critical step for catalysis. Simple electrochemical ammonia production reactors were designed and built in this project using two novel electrolyte systems. The first one demonstrated the use of ionic liquid electrolytes at room temperature and the second the use of pyrophosphate based electrolytes at intermediate temperatures (200 – 300 ºC). The mechanism of high proton conduction in the pyrophosphate materials was found to be associated with a polyphosphate second phase contrary to literature claims and ammonia production rates as high as 5X 10-8 mol/s/cm2 were achieved.

  14. Energy storage, Thermal energy storage (TES)

    E-Print Network [OSTI]

    Zevenhoven, Ron

    Energy storage, Thermal energy storage (TES) Ron Zevenhoven Åbo Akademi University Thermal and Flow 8, 20500 Turku 2/32 4.1 Energy storage #12;Energy storage - motivations Several reasons motivate the storage of energy, either as heat, cold, or electricity: ­ Supplies of energy are in many cases

  15. AQUIFER THERMAL ENERGY STORAGE

    E-Print Network [OSTI]

    Tsang, C.-F.

    2011-01-01

    aquifers for thermal energy storage. Problems outlined abovean Aquifer Used for Hot Water Storage: Digital Simulation ofof Aquifer Systems for Cyclic Storage of Water," of the Fall

  16. AQUIFER THERMAL ENERGY STORAGE

    E-Print Network [OSTI]

    Tsang, C.-F.

    2011-01-01

    of such an aquifer thermal storage system were studied andusing aquifers for thermal energy storage. Problems outlinedmatical Modeling of Thermal Energy Storage in Aquifers,"

  17. Stasis: Flexible Transactional Storage

    E-Print Network [OSTI]

    Sears, Russell C.

    2009-01-01

    AutoRAID hierarchical storage system,” in SOSP, 1995. [147]next-generation storage systems, and to use segments andclasses of distributed storage systems. Bibliography [1] D.

  18. SUPERCONDUCTING MAGNETIC ENERGY STORAGE

    E-Print Network [OSTI]

    Hassenzahl, W.

    2011-01-01

    Superconducting 30-MJ Energy Storage Coil", Proc. 19 80 ASC,Superconducting Magnetic Energy Storage Plant", IEEE Trans.SlIperconducting Magnetic Energy Storage Unit", in Advances

  19. AQUIFER THERMAL ENERGY STORAGE

    E-Print Network [OSTI]

    Tsang, C.-F.

    2011-01-01

    aquifers for thermal energy storage. Problems outlined aboveModeling of Thermal Energy Storage in Aquifers," Proceed-ings of Aquifer Thermal Energy Storage Workshop, Lawrence

  20. DOE Accident Prevention and Investigation Program | Department...

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

    for improvement of our integrated safety management system. The techniques and tools utilized in the investigation of "accidents" can be valuable in looking at leading...

  1. Cool Storage Performance 

    E-Print Network [OSTI]

    Eppelheimer, D. M.

    1985-01-01

    . This article covers three thermal storage topics. The first section catalogs various thermal storage systems and applications. Included are: load shifting and load leveling, chilled water storage systems, and ice storage systems using Refrigerant 22 or ethylene...

  2. ARGX-87: Accident Response Group Exercise, 1987: A Broken Arrow mini exercise. [Training

    SciTech Connect (OSTI)

    Schuld, E.P.; Cruff, D.F.

    1987-07-01

    A Broken Arrow mini exercise dubbed ''Accident Response Group Exercise - 1987'' (ARGX-87) was conducted on June 1, 1987 at the Lawrence Livermore National Laboratory (LLNL) and Sandia National Laboratories, Livermore (SNLL). The exercise started at 0445 PDT with a call from the Department of Energy (DOE) - EOC in Washington, DC, to the Albuquerque Operations (AL - ) - EOC. AL, in turn, called the Laboratory off-hour emergency number (Fire Dispatcher), who called the Laboratory Emergency Duty Officer (LEDO). The LEDO then contacted the Accident Response Group (ARG) Senior Scientific Advisor. Calls were placed to assemble appropriate members of the ARG in the ALERT Center. No phone number for SNLL was available at the Albuquerque Operations EOC, so a controller injected a message to SNLL to get them involved in the exercise. The messages received at the Laboratory identified the Air Force line item weapon system involved in the accident and the accident location. As people arrived at the ALERT Center they began discussing the details of the accident. They also started working the deployment logistics and other issues. Travel arrangements for the HOT SPOT equipment and ARG personnel were made for immediate deployment to the accident site in North Dakota. The exercise was terminated at 0840 as planned. While certain procedural deficiencies were noted, the exercise was considered a valuable learning experience. The results and observations from this experience will be used to refine the operating procedures and the training program.

  3. Does Daylight Savings Time Affect Traffic Accidents

    E-Print Network [OSTI]

    Deen, Sophia 1988-

    2012-04-20

    This paper studies the effect of changes in accident pattern due to Daylight Savings Time (DST). The extension of the DST in 2007 provides a natural experiment to determine whether the number of traffic accidents is affected by shifts in hours...

  4. Light-water reactor accident classification

    SciTech Connect (OSTI)

    Washburn, B.W.

    1980-02-01

    The evolution of existing classifications and definitions of light-water reactor accidents is considered. Licensing practice and licensing trends are examined with respect to terms of art such as Class 8 and Class 9 accidents. Interim definitions, consistent with current licensing practice and the regulations, are proposed for these terms of art.

  5. Storage System and IBM System Storage

    E-Print Network [OSTI]

    IBM® XIV® Storage System and IBM System Storage® SAN Volume Controller deliver high performance and smart management for SAP® landscapes IBM SAP International Competence Center #12;"The combination of the XIV Storage System and SAN Volume Controller gives us a smarter way to manage our storage. If we need

  6. The Fukushima Daiichi Accident Study Information Portal

    SciTech Connect (OSTI)

    Shawn St. Germain; Curtis Smith; David Schwieder; Cherie Phelan

    2012-11-01

    This paper presents a description of The Fukushima Daiichi Accident Study Information Portal. The Information Portal was created by the Idaho National Laboratory as part of joint NRC and DOE project to assess the severe accident modeling capability of the MELCOR analysis code. The Fukushima Daiichi Accident Study Information Portal was created to collect, store, retrieve and validate information and data for use in reconstructing the Fukushima Daiichi accident. In addition to supporting the MELCOR simulations, the Portal will be the main DOE repository for all data, studies and reports related to the accident at the Fukushima Daiichi nuclear power station. The data is stored in a secured (password protected and encrypted) repository that is searchable and accessible to researchers at diverse locations.

  7. Commercial SNF Accident Release Fractions

    SciTech Connect (OSTI)

    J. Schulz

    2004-11-05

    The purpose of this analysis is to specify and document the total and respirable fractions for radioactive materials that could be potentially released from an accident at the repository involving commercial spent nuclear fuel (SNF) in a dry environment. The total and respirable release fractions are used to support the preclosure licensing basis for the repository. The total release fraction is defined as the fraction of total commercial SNF assembly inventory, typically expressed as an activity inventory (e.g., curies), of a given radionuclide that is released to the environment from a waste form. Radionuclides are released from the inside of breached fuel rods (or pins) and from the detachment of radioactive material (crud) from the outside surfaces of fuel rods and other components of fuel assemblies. The total release fraction accounts for several mechanisms that tend to retain, retard, or diminish the amount of radionuclides that are available for transport to dose receptors or otherwise can be shown to reduce exposure of receptors to radiological releases. The total release fraction includes a fraction of airborne material that is respirable and could result in inhalation doses; this subset of the total release fraction is referred to as the respirable release fraction. Accidents may involve waste forms characterized as: (1) bare unconfined intact fuel assemblies, (2) confined intact fuel assemblies, or (3) canistered failed commercial SNF. Confined intact commercial SNF assemblies at the repository are contained in shipping casks, canisters, or waste packages. Four categories of failed commercial SNF are identified: (1) mechanically and cladding-penetration damaged commercial SNF, (2) consolidated/reconstituted assemblies, (3) fuel rods, pieces, and debris, and (4) nonfuel components. It is assumed that failed commercial SNF is placed into waste packages with a mesh screen at each end (CRWMS M&O 1999). In contrast to bare unconfined fuel assemblies, the container that confines the fuel assemblies could provide an additional barrier for diminishing the total release fraction should the fuel rod cladding breach during an accident. This analysis, however, does not take credit for the additional barrier and establishes only the total release fractions for bare unconfined intact commercial SNF assemblies, which may be conservatively applied to confined intact commercial I SNF assemblies.

  8. Accident Investigation of the February 5, 2014, Underground Salt...

    Office of Environmental Management (EM)

    Accident Investigation of the February 5, 2014, Underground Salt Haul Truck Fire at the Waste Isolation Pilot Plant, Carlsbad NM Accident Investigation of the February 5, 2014,...

  9. Development of Light Water Reactor Fuels with Enhanced Accident...

    Energy Savers [EERE]

    Development of Light Water Reactor Fuels with Enhanced Accident Tolerance - Report to Congress Development of Light Water Reactor Fuels with Enhanced Accident Tolerance - Report to...

  10. Type B Accident Investigation Board Report on the October 8,...

    Energy Savers [EERE]

    Bettis Atomic Power Laboratory Type B Accident Investigation of the Arc Flash at Brookhaven National Laboratory, April 14, 2006 Type B Accident Investigation Board Report on...

  11. Type B Accident Investigation Board Report on the November 1...

    Energy Savers [EERE]

    Type B Accident Investigation Board Report on the November 1, 1999, Construction Injury at the Monticello Mill Tailings Remedial Action Site, Monticello, Utah Type B Accident...

  12. Naval Spent Fuel Rail Shipment Accident Exercise Objectives

    Office of Environmental Management (EM)

    NAVAL SPENT FUEL RAIL SHIPMENT ACCIDENT EXERCISE OBJECTIVES * Familiarize stakeholders with the Naval spent fuel ACCIDENT EXERCISE OBJECTIVES Familiarize stakeholders with the...

  13. Accident Investigation of the February 7, 2013, Scissor Lift...

    Energy Savers [EERE]

    Lift Accident in the West Hackberry Brine Tank-14 Resulting in Injury, Strategic Petroleum Reserve West Hackberry, LA Accident Investigation of the February 7, 2013, Scissor...

  14. Type B Accident Investigation of the July 12, 2007, Forklift...

    Energy Savers [EERE]

    2, 2007, Forklift and Pedestrian Accident at the Paducah Gaseous Diffusion Plant, PortsmouthPaducah Project Office Type B Accident Investigation of the July 12, 2007, Forklift and...

  15. ORISE: The Medical Basis for Radiation-Accident Preparedness...

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

    The Medical Basis for Radiation-Accident Preparedness: Medical Management Proceedings of the Fifth International REACTS Symposium on the Medical Basis for Radiation-Accident...

  16. Gas storage materials, including hydrogen storage materials

    DOE Patents [OSTI]

    Mohtadi, Rana F; Wicks, George G; Heung, Leung K; Nakamura, Kenji

    2014-11-25

    A material for the storage and release of gases comprises a plurality of hollow elements, each hollow element comprising a porous wall enclosing an interior cavity, the interior cavity including structures of a solid-state storage material. In particular examples, the storage material is a hydrogen storage material, such as a solid state hydride. An improved method for forming such materials includes the solution diffusion of a storage material solution through a porous wall of a hollow element into an interior cavity.

  17. Gas storage materials, including hydrogen storage materials

    DOE Patents [OSTI]

    Mohtadi, Rana F; Wicks, George G; Heung, Leung K; Nakamura, Kenji

    2013-02-19

    A material for the storage and release of gases comprises a plurality of hollow elements, each hollow element comprising a porous wall enclosing an interior cavity, the interior cavity including structures of a solid-state storage material. In particular examples, the storage material is a hydrogen storage material such as a solid state hydride. An improved method for forming such materials includes the solution diffusion of a storage material solution through a porous wall of a hollow element into an interior cavity.

  18. HAIL: A High-Availability and Integrity Layer for Cloud Storage

    E-Print Network [OSTI]

    International Association for Cryptologic Research (IACR)

    HAIL: A High-Availability and Integrity Layer for Cloud Storage Kevin D. Bowers RSA Laboratories imple- mentation. 1 Introduction Cloud storage denotes a family of increasingly popular on-line services for archiving, backup, and even primary storage of files. Amazon S3 [1] is a well known exam- ple. Cloud-storage

  19. Storage Area Network Optimization A cooperation of Ancor Communications, Minneapolis, USA

    E-Print Network [OSTI]

    Felsner, Stefan

    technology allows concurrent communications among worksta- tions, mainframes, servers, data storage systems delivers a new level of reliability and throughput. Switches, hubs, storage systems, storage devices to one or more storage systems. QLogic o#11;ers a broad product line of SAN infrastructure (see[1]). One

  20. Energy Management for an Onboard Storage System Based on Multi-Objective Optimization

    E-Print Network [OSTI]

    Noé, Reinhold

    Energy Management for an Onboard Storage System Based on Multi-Objective Optimization Tobias Knoke an onboard energy storage, the overhead line peak power and energy consumption can be reduced. The storage. This can be achieved by using an onboard energy storage, which recuperates the power during the braking

  1. Fuel removal, transport, and storage

    SciTech Connect (OSTI)

    Reno, H.W.

    1986-01-01

    The March 1979 accident at Unit 2 of the Three Mile Island Nuclear Power Station (TMI-2) which damaged the core of the reactor resulted in numerous scientific and technical challenges. Some of those challenges involve removing the core debris from the reactor, packaging it into canisters, loading canisters into a rail cask, and transporting the debris to the Idaho National Engineering Laboratory (INEL) for storage, examination, and preparation for final disposal. This paper highlights how some challenges were resolved, including lessons learned and benefits derived therefrom. Key to some success at TMI was designing, testing, fabricating, and licensing two rail casks, which each provide double containment of the damaged fuel. 10 refs., 12 figs.

  2. Storage Statistics

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation ofAlbuquerque|SensitiveAprilPhoton Source Parameters Storage Ringsrlogo_t.gif

  3. Photon Storage Cavities

    E-Print Network [OSTI]

    Kim, K.-J.

    2008-01-01

    Sessler, "Analysis of Photon Storage Cavities for a Free-configuration of coupled storage cavity and PEL cavity. TheFig. 2. A ring resonator storage cavity coupled through a

  4. AQUIFER THERMAL ENERGY STORAGE

    E-Print Network [OSTI]

    Tsang, C.-F.

    2011-01-01

    and Zakhidov, 1971. "Storage of Solar Energy in a Sandy-Aquifer Storage of Hot Water from Solar Energy Collectors,"with solar energy systems, aquifer energy storage provides a

  5. Causal Reasoning About Aircraft Accidents Peter B. Ladkin

    E-Print Network [OSTI]

    Ladkin, Peter B.

    , rigorous causal reasoning in the analysis of air transportation accidents can improve our understanding

  6. COMPARING THE IDENTIFICATION OF RECOMMENDATIONS BY DIFFERENT ACCIDENT

    E-Print Network [OSTI]

    Johnson, Chris

    will be identified for similar incidents. Accident analysis methods can also help to reduce individual bias

  7. Release fractions for Rocky Flats specific accidents

    SciTech Connect (OSTI)

    Weiss, R.C.

    1992-09-01

    As Rocky Flats and other DOE facilities begin the transition process towards decommissioning, the nature of the scenarios to be studied in safety analysis will change. Whereas the previous emphasis in safety accidents related to production, now the emphasis is shifting to accidents related tc decommissioning and waste management. Accident scenarios of concern at Rocky Flats now include situations of a different nature and different scale than are represented by most of the existing experimental accident data. This presentation will discuss approaches@to use for applying the existing body of release fraction data to this new emphasis. Mention will also be made of ongoing efforts to produce new data and improve the understanding of physical mechanisms involved.

  8. Crediting Tritium Deposition in Accident Analysis

    SciTech Connect (OSTI)

    Murphy, C.E. Jr.

    2001-06-20

    This paper describes the major aspects of tritium dispersion phenomenology, summarizes deposition attributes of the computer models used in the DOE Complex for tritium dispersion, and recommends an approach to account for deposition in accident analysis.

  9. A systems approach to food accident analysis

    E-Print Network [OSTI]

    Helferich, John D

    2011-01-01

    Food borne illnesses lead to 3000 deaths per year in the United States. Some industries, such as aviation, have made great strides increasing safety through careful accident analysis leading to changes in industry practices. ...

  10. AQUIFER THERMAL ENERGY STORAGE

    E-Print Network [OSTI]

    Tsang, C.-F.

    2011-01-01

    varying solar energy inputs and thermal or power demands. Itusing aquifers for thermal energy storage. Problems outlinedmatical Modeling of Thermal Energy Storage in Aquifers,"

  11. SUPERCONDUCTING MAGNETIC ENERGY STORAGE

    E-Print Network [OSTI]

    Hassenzahl, W.

    2011-01-01

    to MW/40 MWI-IR Battery Energy Storage Facility", proc. 23rdcompressed air, and battery energy storage are all only 65

  12. Uncertainties and severe-accident management

    SciTech Connect (OSTI)

    Kastenberg, W.E. (Univ. of California, Los Angeles (United States))

    1991-01-01

    Severe-accident management can be defined as the use of existing and or alternative resources, systems, and actions to prevent or mitigate a core-melt accident. Together with risk management (e.g., changes in plant operation and/or addition of equipment) and emergency planning (off-site actions), accident management provides an extension of the defense-indepth safety philosophy for severe accidents. A significant number of probabilistic safety assessments have been completed, which yield the principal plant vulnerabilities, and can be categorized as (a) dominant sequences with respect to core-melt frequency, (b) dominant sequences with respect to various risk measures, (c) dominant threats that challenge safety functions, and (d) dominant threats with respect to failure of safety systems. Severe-accident management strategies can be generically classified as (a) use of alternative resources, (b) use of alternative equipment, and (c) use of alternative actions. For each sequence/threat and each combination of strategy, there may be several options available to the operator. Each strategy/option involves phenomenological and operational considerations regarding uncertainty. These include (a) uncertainty in key phenomena, (b) uncertainty in operator behavior, (c) uncertainty in system availability and behavior, and (d) uncertainty in information availability (i.e., instrumentation). This paper focuses on phenomenological uncertainties associated with severe-accident management strategies.

  13. Large Break LOCA Accident Management Strategies for Accidents With Large Containment Leaks

    SciTech Connect (OSTI)

    Sdouz, Gert [ARC Seibersdorf Research GmbH, Viktor Kaplan-Strasse 2, 2700 Wr. Neustadt (Austria)

    2006-07-01

    The goal of this work is the investigation of the influence of different accident management strategies on the thermal-hydraulics in the containment during a Large Break Loss of Coolant Accident with a large containment leak from the beginning of the accident. The increasing relevance of terrorism suggests a closer look at this kind of severe accidents. Normally the course of severe accidents and their associated phenomena are investigated with the assumption of an intact containment from the beginning of the accident. This intact containment has the ability to retain a large part of the radioactive inventory. In these cases there is only a release via a very small leakage due to the un-tightness of the containment up to cavity bottom melt through. This paper represents the last part of a comprehensive study on the influence of accident management strategies on the source term of VVER-1000 reactors. Basically two different accident sequences were investigated: the 'Station Blackout'- sequence and the 'Large Break LOCA'. In a first step the source term calculations were performed assuming an intact containment from the beginning of the accident and no accident management action. In a further step the influence of different accident management strategies was studied. The last part of the project was a repetition of the calculations with the assumption of a damaged containment from the beginning of the accident. This paper concentrates on the last step in the case of a Large Break LOCA. To be able to compare the results with calculations performed years ago the calculations were performed using the Source Term Code Package (STCP), hydrogen explosions are not considered. In this study four different scenarios have been investigated. The main parameter was the switch on time of the spray systems. One of the results is the influence of different accident management strategies on the source term. In the comparison with the sequence with intact containment it was demonstrated that the accident management measures have quite lower consequences. In addition it was shown that in the case of a 'Large Break LOCA'-sequence the intact containment retains the nuclides up to a factor of 20 000. This is much more than in the case of a 'Station Blackout'-sequence. Within the frame of the study 17 source terms have been generated to evaluate in detail accident management strategies for VVER-1000 reactors. (authors)0.

  14. Fuel Storage Facility Final Safety Analysis Report. Revision 1

    SciTech Connect (OSTI)

    Linderoth, C.E.

    1984-03-01

    The Fuel Storage Facility (FSF) is an integral part of the Fast Flux Test Facility. Its purpose is to provide long-term storage (20-year design life) for spent fuel core elements used to provide the fast flux environment in FFTF, and for test fuel pins, components and subassemblies that have been irradiated in the fast flux environment. This Final Safety Analysis Report (FSAR) and its supporting documentation provides a complete description and safety evaluation of the site, the plant design, operations, and potential accidents.

  15. Transportation Storage Interface | Department of Energy

    Office of Environmental Management (EM)

    Storage Interface Transportation Storage Interface Regulation of Future Extended Storage and Transportation. Transportation Storage Interface More Documents & Publications Gap...

  16. Releases of UF{sub 6} to the atmosphere after a potential fire in a cylinder storage yard

    SciTech Connect (OSTI)

    Lombardi, D.A.; Williams, W.R.; Anderson, J.C. [and others

    1997-06-01

    Uranium hexafluoride (UF{sub 6}), a toxic material, is stored in just over 6200 cylinders at the K-25 site in Oak Ridge, Tennessee. The safety analysis report (SAR) for cylinder yard storage operations at the plant required the development of accident scenarios for the potential release of UF{sub 6} to the atmosphere. In accordance with DOE standards and guidance, the general approach taken in this SAR was to examine the functions and contents of the cylinder storage yards to determine whether safety-significant hazards were present for workers in the immediate vicinity, workers on-site, the general public off-site, or the environment. and to evaluate the significance of any hazards that were found. A detailed accident analysis was performed to determine a set of limiting accidents that have potential for off-site consequences. One of the limiting accidents identified in the SAR was the rupture of a cylinder engulfed in a fire.

  17. A Review of Criticality Accidents 2000 Revision

    SciTech Connect (OSTI)

    Thomas P. McLaughlin; Shean P. Monahan; Norman L. Pruvost; Vladimir V. Frolov; Boris G. Ryazanov; Victor I. Sviridov

    2000-05-01

    Criticality accidents and the characteristics of prompt power excursions are discussed. Sixty accidental power excursions are reviewed. Sufficient detail is provided to enable the reader to understand the physical situation, the chemistry and material flow, and when available the administrative setting leading up to the time of the accident. Information on the power history, energy release, consequences, and causes are also included when available. For those accidents that occurred in process plants, two new sections have been included in this revision. The first is an analysis and summary of the physical and neutronic features of the chain reacting systems. The second is a compilation of observations and lessons learned. Excursions associated with large power reactors are not included in this report.

  18. Enhanced Accident Tolerant LWR Fuels: Metrics Development

    SciTech Connect (OSTI)

    Shannon Bragg-Sitton; Lori Braase; Rose Montgomery; Chris Stanek; Robert Montgomery; Lance Snead; Larry Ott; Mike Billone

    2013-09-01

    The Department of Energy (DOE) Fuel Cycle Research and Development (FCRD) Advanced Fuels Campaign (AFC) is conducting research and development on enhanced Accident Tolerant Fuels (ATF) for light water reactors (LWRs). This mission emphasizes the development of novel fuel and cladding concepts to replace the current zirconium alloy-uranium dioxide (UO2) fuel system. The overall mission of the ATF research is to develop advanced fuels/cladding with improved performance, reliability and safety characteristics during normal operations and accident conditions, while minimizing waste generation. The initial effort will focus on implementation in operating reactors or reactors with design certifications. To initiate the development of quantitative metrics for ATR, a LWR Enhanced Accident Tolerant Fuels Metrics Development Workshop was held in October 2012 in Germantown, MD. This paper summarizes the outcome of that workshop and the current status of metrics development for LWR ATF.

  19. Accident progression event tree analysis for postulated severe accidents at N Reactor

    SciTech Connect (OSTI)

    Wyss, G.D.; Camp, A.L.; Miller, L.A.; Dingman, S.E.; Kunsman, D.M. (Sandia National Labs., Albuquerque, NM (USA)); Medford, G.T. (Science Applications International Corp., Albuquerque, NM (USA))

    1990-06-01

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

  20. Advanced Gas Storage Concepts: Technologies for the Future

    SciTech Connect (OSTI)

    Freeway, Katy; Rogers, R.E.; DeVries, Kerry L.; Nieland, Joel D.; Ratigan, Joe L.; Mellegard, Kirby D.

    2000-02-01

    This full text product includes: 1) A final technical report titled Advanced Underground Gas Storage Concepts, Refrigerated-Mined Cavern Storage and presentations from two technology transfer workshops held in 1998 in Houston, Texas, and Pittsburgh, Pennsylvania (both on the topic of Chilled Gas Storage in Mined Caverns); 2) A final technical report titled Natural Gas Hydrates Storage Project, Final Report 1 October 1997 - 31 May 1999; 3) A final technical report titled Natural Gas Hydrates Storage Project Phase II: Conceptual Design and Economic Study, Final Report 9 June - 10 October 1999; 4) A final technical report titled Commerical Potential of Natural Gas Storage in Lined Rock Caverns (LRC) and presentations from a DOE-sponsored workshop on Alternative Gas Storage Technologies, held Feb 17, 2000 in Pittsburgh, PA; and 5) Phase I and Phase II topical reports titled Feasibility Study for Lowering the Minimum Gas Pressure in Solution-Mined Caverns Based on Geomechanical Analyses of Creep-Induced Damage and Healing.

  1. Fuel performance during severe accidents. [PWR

    SciTech Connect (OSTI)

    Buescher, B.J.; Gruen, G.E.; MacDonald, P.E.

    1982-01-01

    As a result of the Three Mile Island Unit-2 (TMI-2) accident, the Nuclear Regulatory Commission has initiated a severe fuel damage test program to evaluate fuel rod and core response during severe accidents similar to TMI-2. This program is underway in the Power Burst Facility at the Idaho National Engineering Laboratory. In preparation for the first test, predictions have been performed using the TRAC-BD1 computer. This paper presents the calculated results showing a slow heatup to 2400 K over 5 hours, and the analysis includes accelerated oxidation of the zirconium cladding at temperatures above 1850 K.

  2. The temporal effect of traffic violations and accidents on accident occurrence 

    E-Print Network [OSTI]

    McKemie, Martha Susan

    1979-01-01

    THE TEMPORAL EFFECT OF TRAFFIC VIOLATIONS AND ACCIDENTS ON ACCIDENT OCCURRENCE A Thesis by . 1artha Susan McKemie Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirement for the degree of MASTER... OF SCIENCE December 1979 Major Subject: Industrial Engineering THE TEMPORAL El'FECT OF TRAI'FIC VIOIATIONS AND ACCIDENTS ON XCCIDENT OCCURPEENCE A Thesis by Martha Susan McKemie Approved as to style and content by: / ~J' (Chairman of Commi tee...

  3. SACO-1: a fast-running LMFBR accident-analysis code

    SciTech Connect (OSTI)

    Mueller, C.J.; Cahalan, J.E.; Vaurio, J.K.

    1980-01-01

    SACO is a fast-running computer code that simulates hypothetical accidents in liquid-metal fast breeder reactors to the point of permanent subcriticality or to the initiation of a prompt-critical excursion. In the tradition of the SAS codes, each subassembly is modeled by a representative fuel pin with three distinct axial regions to simulate the blanket and core regions. However, analytic and integral models are used wherever possible to cut down the computing time and storage requirements. The physical models and basic equations are described in detail. Comparisons of SACO results to analogous SAS3D results comprise the qualifications of SACO and are illustrated and discussed.

  4. Evaluation of Radiation Impacts of Spent Nuclear Fuel Storage (SNFS-2) of Chernobyl NPP - 13495

    SciTech Connect (OSTI)

    Paskevych, Sergiy; Batiy, Valiriy; Sizov, Andriy; Schmieman, Eric

    2013-07-01

    Radiation effects are estimated for the operation of a new dry storage facility for spent nuclear fuel (SNFS-2) of Chernobyl NPP RBMK reactors. It is shown that radiation exposure during normal operation, design and beyond design basis accidents are minor and meet the criteria for safe use of radiation and nuclear facilities in Ukraine. (authors)

  5. Type B Accident Investigation, Response to the 24 Command Wildland...

    Energy Savers [EERE]

    Type B Accident Investigation, Response to the 24 Command Wildland Fire on the Hanford Site, June 27-July 1, 2000 Type B Accident Investigation, Response to the 24 Command Wildland...

  6. PNNL Results from 2009 Silene Criticality Accident Dosimeter Intercomparison Exercise

    SciTech Connect (OSTI)

    Hill, Robin L.; Conrady, Matthew M.

    2010-06-30

    This document reports the results of testing of the Hanford Personnel Nuclear Accident Dosimeter (PNAD) during a criticality accident dosimeter intercomparison exercise at the CEA Valduc Center on October 13, 14, and 15, 2009.

  7. Developing a knowledge base for the management of severe accidents

    SciTech Connect (OSTI)

    Nelson, W.R.; Jenkins, J.P.

    1986-01-01

    Prior to the accident at Three Mile Island, little attention was given to the development of procedures for the management of severe accidents, that is, accidents in which the reactor core is damaged. Since TMI, however, significant effort has been devoted to developing strategies for severe accident management. At the same time, the potential application of artificial intelligence techniques, particularly expert systems, to complex decision-making tasks such as accident diagnosis and response has received considerable attention. The need to develop strategies for accident management suggests that a computerized knowledge base such as used by an expert system could be developed to collect and organize knowledge for severe accident management. This paper suggests a general method which could be used to develop such a knowledge base, and how it could be used to enhance accident management capabilities.

  8. Distributed storage with communication costs

    E-Print Network [OSTI]

    Armstrong, Craig Kenneth

    2011-01-01

    5 Introduction to Coding for Distributed Storage The Repairflow graph for 1 repair with varying storage capac- itythe Capacity of Storage Nodes . . . 4.1 Characterizing

  9. ACCIDENT ANALYSIS AND HAZARD ANALYSIS FOR HUMAN AND ORGANIZATIONAL FACTORS

    E-Print Network [OSTI]

    Leveson, Nancy

    culpable. An accident analysis method is needed that will guide the work, aid in the analysis of the role

  10. SL-1 Accident Briefing Report - 1961 Nuclear Reactor Meltdown Educational Documentary

    ScienceCinema (OSTI)

    None

    2014-03-11

    U.S. Atomic Energy Commission (Idaho Operations Office) briefing about the SL-1 Nuclear Reactor Meltdown. The SL-1, or Stationary Low-Power Reactor Number One, was a United States Army experimental nuclear power reactor which underwent a steam explosion and meltdown on January 3, 1961, killing its three operators. The direct cause was the improper withdrawal of the central control rod, responsible for absorbing neutrons in the reactor core. The event is the only known fatal reactor accident in the United States. The accident released about 80 curies (3.0 TBq) of Iodine-131, which was not considered significant due to its location in a remote desert of Idaho. About 1,100 curies (41 TBq) of fission products were released into the atmosphere. The facility, located at the National Reactor Testing Station approximately 40 miles (64 km) west of Idaho Falls, Idaho, was part of the Army Nuclear Power Program and was known as the Argonne Low Power Reactor (ALPR) during its design and build phase. It was intended to provide electrical power and heat for small, remote military facilities, such as radar sites near the Arctic Circle, and those in the DEW Line. The design power was 3 MW (thermal). Operating power was 200 kW electrical and 400 kW thermal for space heating. In the accident, the core power level reached nearly 20 GW in just four milliseconds, precipitating the reactor accident and steam explosion.

  11. SL-1 Accident Briefing Report - 1961 Nuclear Reactor Meltdown Educational Documentary

    SciTech Connect (OSTI)

    2013-09-25

    U.S. Atomic Energy Commission (Idaho Operations Office) briefing about the SL-1 Nuclear Reactor Meltdown. The SL-1, or Stationary Low-Power Reactor Number One, was a United States Army experimental nuclear power reactor which underwent a steam explosion and meltdown on January 3, 1961, killing its three operators. The direct cause was the improper withdrawal of the central control rod, responsible for absorbing neutrons in the reactor core. The event is the only known fatal reactor accident in the United States. The accident released about 80 curies (3.0 TBq) of Iodine-131, which was not considered significant due to its location in a remote desert of Idaho. About 1,100 curies (41 TBq) of fission products were released into the atmosphere. The facility, located at the National Reactor Testing Station approximately 40 miles (64 km) west of Idaho Falls, Idaho, was part of the Army Nuclear Power Program and was known as the Argonne Low Power Reactor (ALPR) during its design and build phase. It was intended to provide electrical power and heat for small, remote military facilities, such as radar sites near the Arctic Circle, and those in the DEW Line. The design power was 3 MW (thermal). Operating power was 200 kW electrical and 400 kW thermal for space heating. In the accident, the core power level reached nearly 20 GW in just four milliseconds, precipitating the reactor accident and steam explosion.

  12. Redesigning experimental equipment for determining peak pressure in a simulated tank car transfer line

    E-Print Network [OSTI]

    Diaz, Richard A

    2007-01-01

    When liquids are transported from storage tanks to tank cars, improper order of valve openings can cause pressure surges in the transfer line. To model this phenomenon and predict the peak pressures in such a transfer line, ...

  13. INTERNATIONAL STUDENT & SCHOLAR Accident & Sickness Insurance Plan

    E-Print Network [OSTI]

    Bordenstein, Seth

    and scholars participating in international educational programs outside of the United States. It is strongly an accident and sickness insurance plan for international students and scholars studying in the United States. The International Student & Scholar plan has a low monthly rate of $70 per person. WE'VE GOT YOU COVERED

  14. Severe Accident Test Station Activity Report

    SciTech Connect (OSTI)

    Pint, Bruce A.; Terrani, Kurt A.

    2015-06-01

    Enhancing safety margins in light water reactor (LWR) severe accidents is currently the focus of a number of international R&D programs. The current UO2/Zr-based alloy fuel system is particularly susceptible since the Zr-based cladding experiences rapid oxidation kinetics in steam at elevated temperatures. Therefore, alternative cladding materials that offer slower oxidation kinetics and a smaller enthalpy of oxidation can significantly reduce the rate of heat and hydrogen generation in the core during a coolant-limited severe accident. In the U.S. program, the high temperature steam oxidation performance of accident tolerant fuel (ATF) cladding solutions has been evaluated in the Severe Accident Test Station (SATS) at Oak Ridge National Laboratory (ORNL) since 2012. This report summarizes the capabilities of the SATS and provides an overview of the oxidation kinetics of several candidate cladding materials. A suggested baseline for evaluating ATF candidates is a two order of magnitude reduction in the steam oxidation resistance above 1000ºC compared to Zr-based alloys. The ATF candidates are categorized based on the protective external oxide or scale that forms during exposure to steam at high temperature: chromia, alumina, and silica. Comparisons are made to literature and SATS data for Zr-based alloys and other less-protective materials.

  15. Characterization of a nuclear accident dosimeter 

    E-Print Network [OSTI]

    Burrows, Ronald Allen

    1995-01-01

    The 23rd nuclear accident dosimetry intercomparison was held during the week of June 12-16, 1995 at Los Alamos National Laboratory. This report presents the results of this event, referred to as NAD 23, as related to the performance of Sandia...

  16. Accident or Design Taeil A. Bai

    E-Print Network [OSTI]

    Bai, Taeil

    to this principle, a life-giving factor lies at the center of the whole machinery and design of the world. Here weAccident or Design Taeil A. Bai Stanford University, Stanford, CA 94305 In a companion article find the word "design," which has been expelled from biological scholarship by the biologists. Here we

  17. SUPERCONDUCTING MAGNETIC ENERGY STORAGE

    E-Print Network [OSTI]

    Hassenzahl, W.

    2011-01-01

    based on applications on dc transmission lines 30 . Throughcontrol to an existing dc transmission line to provide the

  18. L'accident la centrale nuclaire de Quelques explications scientifiques

    E-Print Network [OSTI]

    Skorobogatiy, Maksim

    L'accident à la centrale nucléaire de Fukushima Quelques explications scientifiques G. Marleau, J´eal, 18 mars 2011 L'accident `a la centrale nucl´eaire de Fukushima ­ 1/29 Accident de Fukushima 1 Contenu de Fukushima. 3. La puissance résiduelle. 4. Perte de refroidissement et conséquences. 5

  19. Louisiana Forest Products Lab 1 Accidents in the Primary &

    E-Print Network [OSTI]

    Louisiana Forest Products Lab 1 Accidents in the Primary & Secondary Forest Products Industry Center #12;Louisiana Forest Products Lab 2 Abitibi Paper Co. Camp 40 Thunder Bay, Ontario #12;Louisiana Forest Products Lab 3 Accidents in Forest Products Industry Accident Statistics Primary industry

  20. Pumped Storage Hydropower

    Broader source: Energy.gov [DOE]

    In addition to traditional hydropower, pumped-storage hydropower (PSH)—A type of hydropower that works like a battery, pumping water from a lower reservoir to an upper reservoir for storage and...

  1. Multiported storage devices 

    E-Print Network [OSTI]

    Grande, Marcus Bryan

    2000-01-01

    and intelligence than the traditional block storage device. A multiported storage device allows application-specific code that we call filter applets to be downloaded to the device while still maintaining the simple block-level interface. The device contains...

  2. Transportation Storage Interface

    Office of Environmental Management (EM)

    in above- ground bunkers, each of which is about the size of a one-car garage. Spent Fuel Storage: Dual Purpose Cask Systems 8 Spent Fuel Storage and Transportation: Framework...

  3. Unit 35 - Raster Storage

    E-Print Network [OSTI]

    Unit 35, CC in GIS; Peuquet, Donna

    1990-01-01

    in GIS - 1990 Page 8 Unit 35 - Raster Storage GIS to whichNCGIA Core Curriculum in GIS - 1990 Page 9 Unit 35 - RasterStorage UNIT 35 IMAGES NCGIA Core Curriculum in GIS - 1990

  4. Energy Storage Systems

    SciTech Connect (OSTI)

    Conover, David R.

    2013-12-01

    Energy Storage Systems – An Old Idea Doing New Things with New Technology article for the International Assoication of ELectrical Inspectors

  5. Accountable Storage Giuseppe Ateniese

    E-Print Network [OSTI]

    International Association for Cryptologic Research (IACR)

    Accountable Storage Giuseppe Ateniese Michael T. Goodrich Vassilios Lekakis Charalampos Papamanthou§ Evripidis Paraskevas§ Roberto Tamassia¶ Abstract We introduce Accountable Storage (AS), a framework allowing. Such protocols offer "provable storage insurance" to a client: In case of a data loss, the client can

  6. Electric utility applications of hydrogen energy storage systems

    SciTech Connect (OSTI)

    Swaminathan, S.; Sen, R.K.

    1997-10-15

    This report examines the capital cost associated with various energy storage systems that have been installed for electric utility application. The storage systems considered in this study are Battery Energy Storage (BES), Superconducting Magnetic Energy Storage (SMES) and Flywheel Energy Storage (FES). The report also projects the cost reductions that may be anticipated as these technologies come down the learning curve. This data will serve as a base-line for comparing the cost-effectiveness of hydrogen energy storage (HES) systems in the electric utility sector. Since pumped hydro or compressed air energy storage (CAES) is not particularly suitable for distributed storage, they are not considered in this report. There are no comparable HES systems in existence in the electric utility sector. However, there are numerous studies that have assessed the current and projected cost of hydrogen energy storage system. This report uses such data to compare the cost of HES systems with that of other storage systems in order to draw some conclusions as to the applications and the cost-effectiveness of hydrogen as a electricity storage alternative.

  7. Groundwater and Terrestrial Water Storage

    E-Print Network [OSTI]

    Rodell, M; Chambers, D P; Famiglietti, J S

    2011-01-01

    T. E. Reilly, 2002: Flow and storage in groundwater systems.Estimating ground water storage changes in the Mississippistorage..

  8. REAC/TS Radiation Accident Registry: An Overview

    SciTech Connect (OSTI)

    Doran M. Christensen, DO, REAC /TS Associate Director and Staff Physician Becky Murdock, REAC/TS Registry and Health Physics Technician

    2012-12-12

    Over the past four years, REAC/TS has presented a number of case reports from its Radiation Accident Registry. Victims of radiological or nuclear incidents must meet certain dose criteria for an incident to be categorized as an “accident” and be included in the registry. Although the greatest numbers of “accidents” in the United States that have been entered into the registry involve radiation devices, the greater percentage of serious accidents have involved sealed sources of one kind or another. But if one looks at the kinds of accident scenarios that have resulted in extreme consequence, i.e., death, the greater share of deaths has occurred in medical settings.

  9. Storage Ring Revised March 1994

    E-Print Network [OSTI]

    Brookhaven National Laboratory - Experiment 821

    Chapter 8. Storage Ring Revised March 1994 8.1. Introduction -- 107 -- #12; 108 Storage Ring 8.2. Magnetic Design and Field Calculations 8.2.1. Conceptual Approach #12; Storage Ring 109 #12; 110 Storage Ring 8.2.2. Computer Aided Refined Pole Designs #12; Storage Ring 111 #12; 112 Storage Ring #12

  10. Storage : DAS / SAN / NAS Dploiement

    E-Print Network [OSTI]

    Collette. Sébastien

    CH8 Divers 2 Agenda · Storage : DAS / SAN / NAS · Déploiement · VLAN ­ 802.1Q · Gestion d · Sécurisation de Windows · Sécurisation de UNIX · Qu'est-ce que... ­ Firewall, VPN, IDS/IPS, PKI Storage : DAS, NAS, SAN #12;3 Storage : DAS, NAS, SAN · Direct Attached Storage · Network Attached Storage · Storage

  11. Arrival condition of spent fuel after storage, handling, and transportation

    SciTech Connect (OSTI)

    Bailey, W.J.; Pankaskie, P.J.; Langstaff, D.C.; Gilbert, E.R.; Rising, K.H.; Schreiber, R.E.

    1982-11-01

    This report presents the results of a study conducted to determine the probable arrival condition of spent light-water reactor (LWR) fuel after handling and interim storage in spent fuel storage pools and subsequent handling and accident-free transport operations under normal or slightly abnormal conditions. The objective of this study was to provide information on the expected condition of spent LWR fuel upon arrival at interim storage or fuel reprocessing facilities or at disposal facilities if the fuel is declared a waste. Results of a literature survey and data evaluation effort are discussed. Preliminary threshold limits for storing, handling, and transporting unconsolidated spent LWR fuel are presented. The difficulty in trying to anticipate the amount of corrosion products (crud) that may be on spent fuel in future shipments is also discussed, and potential areas for future work are listed. 95 references, 3 figures, 17 tables.

  12. NSLS-II Transport Line Progress

    SciTech Connect (OSTI)

    Fliller R. P.; Wahl, W.; Anderson, A.; Benish, B.; DeBoer, W.; Ganetis, G.; Heese, R.; Hseuh, H.-C.; Hu, J.-P.; Johanson, M.P.; Kosciuk, B.N.; Padrazo, D.; Roy, K.; Shaftan, T.; Singh, O.; Tuozzolo, J.; Wang, G.

    2012-05-20

    The National Synchrotron Light Source II (NSLS-II) is a state-of-the-art 3-GeV third generation light source currently under construction at Brookhaven National Laboratory. The NSLS-II injection system consists of a 200 MeV linac, a 3-GeV booster synchrotron and associated transfer lines. The first part of the Linac to Booster Transport (LBT) line has been installed for linac commissioning. This part includes all components necessary to commission the NSLS-II linac. The second part of this transport line is undergoing installation. Initial results of hardware commissioning will be discussed. The Booster to Storage Ring (BSR) transport line underwent a design review. The first part of the BSR transport line, consisting of all components necessary to commission the booster will be installed in 2012 for booster commissioning. We report on the final design of the BSR line along with the plan to commission the booster.

  13. Evaluation Metrics Applied to Accident Tolerant Fuels

    SciTech Connect (OSTI)

    Shannon M. Bragg-Sitton; Jon Carmack; Frank Goldner

    2014-10-01

    The safe, reliable, and economic operation of the nation’s nuclear power reactor fleet has always been a top priority for the United States’ nuclear industry. Continual improvement of technology, including advanced materials and nuclear fuels, remains central to the industry’s success. Decades of research combined with continual operation have produced steady advancements in technology and have yielded an extensive base of data, experience, and knowledge on light water reactor (LWR) fuel performance under both normal and accident conditions. One of the current missions of the U.S. Department of Energy’s (DOE) Office of Nuclear Energy (NE) is to develop nuclear fuels and claddings with enhanced accident tolerance for use in the current fleet of commercial LWRs or in reactor concepts with design certifications (GEN-III+). Accident tolerance became a focus within advanced LWR research upon direction from Congress following the 2011 Great East Japan Earthquake, resulting tsunami, and subsequent damage to the Fukushima Daiichi nuclear power plant complex. The overall goal of ATF development is to identify alternative fuel system technologies to further enhance the safety, competitiveness and economics of commercial nuclear power. Enhanced accident tolerant fuels would endure loss of active cooling in the reactor core for a considerably longer period of time than the current fuel system while maintaining or improving performance during normal operations. The U.S. DOE is supporting multiple teams to investigate a number of technologies that may improve fuel system response and behavior in accident conditions, with team leadership provided by DOE national laboratories, universities, and the nuclear industry. Concepts under consideration offer both evolutionary and revolutionary changes to the current nuclear fuel system. Mature concepts will be tested in the Advanced Test Reactor at Idaho National Laboratory beginning in Summer 2014 with additional concepts being readied for insertion in fiscal year 2015. This paper provides a brief summary of the proposed evaluation process that would be used to evaluate and prioritize the candidate accident tolerant fuel concepts currently under development.

  14. Severe accident approach - final report. Evaluation of design measures for severe accident prevention and consequence mitigation.

    SciTech Connect (OSTI)

    Tentner, A. M.; Parma, E.; Wei, T.; Wigeland, R.; Nuclear Engineering Division; SNL; INL

    2010-03-01

    An important goal of the US DOE reactor development program is to conceptualize advanced safety design features for a demonstration Sodium Fast Reactor (SFR). The treatment of severe accidents is one of the key safety issues in the design approach for advanced SFR systems. It is necessary to develop an in-depth understanding of the risk of severe accidents for the SFR so that appropriate risk management measures can be implemented early in the design process. This report presents the results of a review of the SFR features and phenomena that directly influence the sequence of events during a postulated severe accident. The report identifies the safety features used or proposed for various SFR designs in the US and worldwide for the prevention and/or mitigation of Core Disruptive Accidents (CDA). The report provides an overview of the current SFR safety approaches and the role of severe accidents. Mutual understanding of these design features and safety approaches is necessary for future collaborations between the US and its international partners as part of the GEN IV program. The report also reviews the basis for an integrated safety approach to severe accidents for the SFR that reflects the safety design knowledge gained in the US during the Advanced Liquid Metal Reactor (ALMR) and Integral Fast Reactor (IFR) programs. This approach relies on inherent reactor and plant safety performance characteristics to provide additional safety margins. The goal of this approach is to prevent development of severe accident conditions, even in the event of initiators with safety system failures previously recognized to lead directly to reactor damage.

  15. US Department of Energy Chernobyl accident bibliography

    SciTech Connect (OSTI)

    Kennedy, R A; Mahaffey, J A; Carr, F Jr

    1992-04-01

    This bibliography has been prepared by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE) Office of Health and Environmental Research to provide bibliographic information in a usable format for research studies relating to the Chernobyl nuclear accident that occurred in the Ukrainian Republic, USSR in 1986. This report is a product of the Chernobyl Database Management project. The purpose of this project is to produce and maintain an information system that is the official United States repository for information related to the accident. Two related products prepared for this project are the Chernobyl Bibliographic Search System (ChernoLit{trademark}) and the Chernobyl Radiological Measurements Information System (ChernoDat). This report supersedes the original release of Chernobyl Bibliography (Carr and Mahaffey, 1989). The original report included about 2200 references. Over 4500 references and an index of authors and editors are included in this report.

  16. Risk Estimation Methodology for Launch Accidents.

    SciTech Connect (OSTI)

    Clayton, Daniel James; Lipinski, Ronald J.; Bechtel, Ryan D.

    2014-02-01

    As compact and light weight power sources with reliable, long lives, Radioisotope Power Systems (RPSs) have made space missions to explore the solar system possible. Due to the hazardous material that can be released during a launch accident, the potential health risk of an accident must be quantified, so that appropriate launch approval decisions can be made. One part of the risk estimation involves modeling the response of the RPS to potential accident environments. Due to the complexity of modeling the full RPS response deterministically on dynamic variables, the evaluation is performed in a stochastic manner with a Monte Carlo simulation. The potential consequences can be determined by modeling the transport of the hazardous material in the environment and in human biological pathways. The consequence analysis results are summed and weighted by appropriate likelihood values to give a collection of probabilistic results for the estimation of the potential health risk. This information is used to guide RPS designs, spacecraft designs, mission architecture, or launch procedures to potentially reduce the risk, as well as to inform decision makers of the potential health risks resulting from the use of RPSs for space missions.

  17. Method of assessing severe accident management strategies

    SciTech Connect (OSTI)

    Kastenberg, W.E.; Apostolakis, G.; Dhir, V.K.; Okrent, D.; Jae, M.; Lim, H.; Milici, T.; Park, H.; Swider, J.; Xing, L.; Yu, D. (Univ. of California, Los Angeles (United States))

    1991-01-01

    Accident management can be defined as the innovative use of existing and or alternative resources, systems, and actions to prevent or mitigate a severe accident. A significant number of probabilistic safety assessments (PSAs) have been completed that yield the principal plant vulnerabilities. These vulnerabilities can be categorized as (1) dominant sequences with respect to core-melt frequency. (2) dominant sequences with respect to various risk measures. (3) dominant threats that challenge safety functions. (4) dominant threats with respect to failure of safety systems. For each sequence/threat and each combination of strategy, there may be several options available to the operator. Each strategy/option involves phenomenological and operational considerations regarding uncertainty. These considerations include uncertainties in key phenomena, operator behavior, system availability and behavior, and available information. This paper presents a methodology for assessing severe accident management strategies given the key uncertainties delineated at two workshops held at the University of California, Los Angeles. Based on decision trees and influence diagrams, the methodology is currently being applied to two case studies: cavity flooding in a pressurized water reactor (PWR) to prevent vessel penetration or failure, and drywell flooding in a boiling water reactor to prevent vessel and/or containment failure.

  18. Investigations on optimization of accident management measures following a station blackout accident in a VVER-1000 pressurized water reactor

    SciTech Connect (OSTI)

    Tusheva, P.; Schaefer, F.; Kliem, S. [Helmholtz-Zentrum Dresden-Rossendorf, Bautzner Landstrasse 400, D-01328 Dresden (Germany)

    2012-07-01

    The reactor safety issues are of primary importance for preserving the health of the population and ensuring no release of radioactivity and fission products into the environment. A part of the nuclear research focuses on improvement of the safety of existing nuclear power plants. Studies, research and efforts are a continuing process at improving the safety and reliability of existing and newly developed nuclear power plants at prevention of a core melt accident. Station blackout (loss of AC power supply) is one of the dominant accidents taken into consideration at performing accident analysis. In case of multiple failures of safety systems it leads to a severe accident. To prevent an accident to turn into a severe one or to mitigate the consequences, accident management measures must be performed. The present paper outlines possibilities for application and optimization of accident management measures following a station blackout accident. Assessed is the behaviour of the nuclear power plant during a station blackout accident without accident management measures and with application of primary/secondary side oriented accident management measures. Discussed are the possibilities for operators ' intervention and the influence of the performed accident management measures on the course of the accident. Special attention has been paid to the effectiveness of the passive feeding and physical phenomena having an influence on the system behaviour. The performed simulations show that the effectiveness of the secondary side feeding procedure can be limited due to an early evaporation or flashing effects in the feed water system. The analyzed cases show that the effectiveness of the accident management measures strongly depends on the initiation criteria applied for depressurization of the reactor coolant system. (authors)

  19. Heat storage duration

    SciTech Connect (OSTI)

    Balcomb, J.D.

    1981-01-01

    Both the amount and duration of heat storage in massive elements of a passive building are investigated. Data taken for one full winter in the Balcomb solar home are analyzed with the aid of sub-system simulation models. Heat storage duration is tallied into one-day intervals. Heat storage location is discussed and related to overall energy flows. The results are interpreted and conclusions drawn.

  20. Interim Storage of Plutonium in Existing Facilities

    SciTech Connect (OSTI)

    Woodsmall, T.D.

    1999-05-10

    'In this era of nuclear weapons disarmament and nonproliferation treaties, among many problems being faced by the Department of Energy is the safe disposal of plutonium. There is a large stockpile of plutonium at the Rocky Flats Environmental Technology Center and it remains politically and environmentally strategic to relocate the inventory closer to a processing facility. Savannah River Site has been chosen as the final storage location, and the Actinide Packaging and Storage Facility (APSF) is currently under construction for this purpose. With the ability of APSF to receive Rocky Flats material an estimated ten years away, DOE has decided to use the existing reactor building in K-Area of SRS as temporary storage to accelerate the removal of plutonium from Rocky Flats. There are enormous cost savings to the government that serve as incentive to start this removal as soon as possible, and the KAMS project is scheduled to receive the first shipment of plutonium in January 2000. The reactor building in K-Area was chosen for its hardened structure and upgraded seismic qualification, both resulting from an effort to restart the reactor in 1991. The KAMS project has faced unique challenges from Authorization Basis and Safety Analysis perspectives. Although modifying a reactor building from a production facility to a storage shelter is not technically difficult, the nature of plutonium has caused design and safety analysis engineers to make certain that the design of systems, structures and components included will protect the public, SRS workers, and the environment. A basic overview of the KAMS project follows. Plutonium will be measured and loaded into DOT Type-B shipping packages at Rocky Flats. The packages are 35-gallon stainless steel drums with multiple internal containment boundaries. DOE transportation vehicles will be used to ship the drums to the KAMS facility at SRS. They will then be unloaded, stacked and stored in specific locations throughout the reactor building. The storage life is projected to be ten years to allow the preparation of APSF. DOE has stipulated that there be no credible release during storage, since there are no design features in place to mitigate a release of plutonium (i.e. HEPA filters, facility containment boundaries, etc.). This mandate has presented most of the significant challenges to the safety analysis team. The shipping packages are designed to withstand certain accidents and conditions, but in order to take credit for these the storage environment must be strictly controlled. Damages to the packages from exposure to fire, dropping, crushing and other impact accidents have been analyzed, and appropriate preventative design features have been incorporated. Other efforts include the extension of the shipping life (roughly two years) to a suitable storage life of ten years. These issues include the effects of internal pressure increases, seal degradation and the presence of impurities. A process known as the Container Qualification Program has been conducted to address these issues. The KAMS project will be ready to receive the first shipment from Rocky Flats in January 2000. No credible design basis scenarios resulting in the release of plutonium exist. This work has been useful in the effort to provide a safer disposition of plutonium, but also the lessons learned and techniques established by the team will help with the analysis of future facility modifications.'

  1. Culex quinquefasciatus Storage Proteins

    E-Print Network [OSTI]

    2013-01-01

    and hemolymph proteins of Cx. quinquefasciatus . A and B:of typical storage proteins in Cx. quinquefasciatus.Fourth-instar Cx. quinquefasciatus larvae and early pupae

  2. Transmission and Storage Operations

    Energy Savers [EERE]

    Transmission and Storage Operations Natural Gas Infrastructure R&D and Methane Mitigation Workshop Mary Savalle, PMP, LSSGB Compression Reliability Engineer November 12, 2014...

  3. SUPERCONDUCTING MAGNETIC ENERGY STORAGE

    E-Print Network [OSTI]

    Hassenzahl, W.

    2011-01-01

    and R. W . BOOIll, "Superconductive Energy Storage Inducand H. A. Peterson, "Superconductive E nergy S torage forMeeting, Janua ry N. Mohan, "Superconductive Energy S torage

  4. HEATS: Thermal Energy Storage

    SciTech Connect (OSTI)

    2012-01-01

    HEATS Project: The 15 projects that make up ARPA-E’s HEATS program, short for “High Energy Advanced Thermal Storage,” seek to develop revolutionary, cost-effective ways to store thermal energy. HEATS focuses on 3 specific areas: 1) developing high-temperature solar thermal energy storage capable of cost-effectively delivering electricity around the clock and thermal energy storage for nuclear power plants capable of cost-effectively meeting peak demand, 2) creating synthetic fuel efficiently from sunlight by converting sunlight into heat, and 3) using thermal energy storage to improve the driving range of electric vehicles (EVs) and also enable thermal management of internal combustion engine vehicles.

  5. Hydrogen Storage Challenges

    Broader source: Energy.gov [DOE]

    For transportation, the overarching technical challenge for hydrogen storage is how to store the amount of hydrogen required for a conventional driving range (>300 miles) within the vehicular...

  6. AQUIFER THERMAL ENERGY STORAGE

    E-Print Network [OSTI]

    Tsang, C.-F.

    2011-01-01

    thermal energy becomes apparent with the development of solarsolar energy systems, aquifer energy storage provides a buffer between time-varying solar energy inputs and thermal

  7. Distributed Generation with Heat Recovery and Storage

    E-Print Network [OSTI]

    Siddiqui, Afzal S.; Marnay, Chris; Firestone, Ryan M.; Zhou, Nan

    2008-01-01

    Weekday Total Electricity Generation (Storage AdoptionWeekday Total Electricity Generation (Storage Adoptionrecovery and storage) utility electricity and natural gas

  8. Developing and assessing accident management plans for nuclear power plants

    SciTech Connect (OSTI)

    Hanson, D.J.; Johnson, S.P.; Blackman, H.S.; Stewart, M.A. (EG and G Idaho, Inc., Idaho Falls, ID (United States))

    1992-07-01

    This document is the second of a two-volume NUREG/CR that discusses development of accident management plans for nuclear power plants. The first volume (a) describes a four-phase approach for developing criteria that could be used for assessing the adequacy of accident management plans, (b) identifies the general attributes of accident management plans (Phase 1), (c) presents a prototype process for developing and implementing severe accident management plans (Phase 2), and (d) presents criteria that can be used to assess the adequacy of accident management plans. This volume (a) describes results from an evaluation of the capabilities of the prototype process to produce an accident management plan (Phase 3) and (b), based on these results and preliminary criteria included in NUREG/CR-5543, presents modifications to the criteria where appropriate.

  9. A framework for the assessment of severe accident management strategies

    SciTech Connect (OSTI)

    Kastenberg, W.E. [ed.; Apostolakis, G.; Dhir, V.K. [California Univ., Los Angeles, CA (United States). Dept. of Mechanical, Aerospace and Nuclear Engineering] [and others

    1993-09-01

    Severe accident management can be defined as the use of existing and/or altemative resources, systems and actors to prevent or mitigate a core-melt accident. For each accident sequence and each combination of severe accident management strategies, there may be several options available to the operator, and each involves phenomenological and operational considerations regarding uncertainty. Operational uncertainties include operator, system and instrumentation behavior during an accident. A framework based on decision trees and influence diagrams has been developed which incorporates such criteria as feasibility, effectiveness, and adverse effects, for evaluating potential severe accident management strategies. The framework is also capable of propagating both data and model uncertainty. It is applied to several potential strategies including PWR cavity flooding, BWR drywell flooding, PWR depressurization and PWR feed and bleed.

  10. Assessment of light water reactor accident management programs and experience

    SciTech Connect (OSTI)

    Hammersley, R.J. [Fauske and Associates, Inc., Burr Ridge, IL (United States)

    1992-03-01

    The objective of this report is to provide an assessment of the current light water reactor experience regarding accident management programs and associated technology developments. This assessment for light water reactor (LWR) designs is provided as a resource and reference for the development of accident management capabilities for the production reactors at the Savannah River Site. The specific objectives of this assessment are as follows: 1. Perform a review of the NRC, utility, and industry (NUMARC, EPRI) accident management programs and implementation experience. 2. Provide an assessment of the problems and opportunities in developing an accident management program in conjunction or following the Individual Plant Examination process. 3. Review current NRC, utility, and industry technological developments in the areas of computational tools, severe accident predictive tools, diagnostic aids, and severe accident training and simulation.

  11. Use of probabilistic safety analyses in severe accident management

    SciTech Connect (OSTI)

    Neogy, P.; Lehner, J.

    1991-01-01

    An important consideration in the development and assessment of severe accident management strategies is that while the strategies are often built on the knowledge base of Probabilistic Safety Analyses (PSA), they must be interpretable and meaningful in terms of the control room indicators. In the following, the relationships between PSA and severe accident management are explored using ex-vessel accident management at a PWR ice-condenser plant as an example. 2 refs., 1 fig., 3 tabs.

  12. Ice Bear® Storage Module | Department of Energy

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

    Ice Bear Storage Module Ice Bear Storage Module Thermal Energy Storage for Light Commercial Refrigerant-Based Air Conditioning Units The Ice Bear storage technology was...

  13. Sandia Energy - Energy Storage Test Pad (ESTP)

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

    Storage Test Pad (ESTP) Home Energy Permalink Gallery Evaluating Powerful Batteries for Modular Electric Grid Energy Storage Energy, Energy Storage, Energy Storage Systems, Energy...

  14. Type B Accident Investigation Board Report of the Brookhaven...

    Energy Savers [EERE]

    of the Brookhaven National Laboratory Employee Injury at Building 1005H on October 9, 2009 Type B Accident Investigation Board Report of the Brookhaven National Laboratory Employee...

  15. Type A Accident Investigation of the March 16, 2000, Plutonium...

    Energy Savers [EERE]

    Multiple Intake Event at the Plutonium Facility, Los Alamos National Laboratory, New Mexico Type A Accident Investigation of the March 16, 2000, Plutonium-238 Multiple Intake...

  16. Type B Accident Investigation Report on the Exertional Heat Illnesses...

    Energy Savers [EERE]

    Heat Illnesses during SPOTC 2006 at the National Training Center in Albuquerque, New Mexico, July 13, 2006 Type B Accident Investigation Report on the Exertional Heat Illnesses...

  17. Type B Accident Investigation Board Report of the September 29...

    Energy Savers [EERE]

    of the September 29, 2010, Radiological Contamination Event at the Separations Process Research Unit (SPRU), Building H2 Demolition, in Niskayuna, New, York Type B Accident...

  18. Accident Investigation of the August 21, 2012, Contamination...

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

    August 21, 2012, Contamination Incident at the Los Alamos Neutron Science Center at the Los Alamos National Laboratory Accident Investigation of the August 21, 2012, Contamination...

  19. Type B Accident Investigation of the October 9, 2008 Employee...

    Energy Savers [EERE]

    October 9, 2008 Employee Injured when Rocket Motor Unexpectedly Fired at the Sandia National Laboratories Technical Area III Sled Track, Sandia Site Office Type B Accident...

  20. Type B Accident Investigation Board Report for the January 11...

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

    a serious injury to his right hand while operating a table saw. In conducting its investigation, the Accident Investigation Board (the Board) used various analytical techniques,...

  1. Type B Accident Investigation Board Report on the October 15...

    Energy Savers [EERE]

    15, 2001, Grout Injection Operator Injury at the Cold Test Pit South, Idaho National Engineering and Environmental Laboratory Type B Accident Investigation Board Report on the...

  2. Summary of a workshop on severe accident management for PWRs

    SciTech Connect (OSTI)

    Kastenberg, W.E. [ed.; Apostolakis, G.; Jae, M.; Milici, T.; Park, H.; Xing, L.; Dhir, V.K.; Lim, H.; Okrent, D.; Swider, J.; Yu, D. [California Univ., Los Angeles, CA (United States). Dept. of Mechanical, Aerospace and Nuclear Engineering

    1991-11-01

    Severe accident management can be defined as the use of existing and/or alternative resources, systems and actions to prevent or mitigate a core-melt accident. For each accident sequence and each combination of strategy, there may be several options available to the operator; and each involves phenomenological and operational considerations regarding uncertainty. Operational uncertainty includes operator, system and instrument behavior during severe accidents. During the period May 15--17, 1990 a workshop was held at the University of California, Los Angeles, to address these uncertainties for pressurized water reactors (PWRs). This report contains a summary of the workshop proceedings.

  3. Summary of a workshop on severe accident management for BWRs

    SciTech Connect (OSTI)

    Kastenberg, W.E. [ed.; Apostolakis, G.; Jae, M.; Milici, T.; Park, H.; Xing, L.; Dhir, V.K.; Lim, H.; Okrent, D.; Swider, J.; Yu, D. [California Univ., Los Angeles, CA (United States). Dept. of Mechanical, Aerospace and Nuclear Engineering

    1991-11-01

    Severe accident management can be defined as the use of existing and/or alternative resources, systems and actions to prevent or mitigate a core-melt accident. For each accident sequence and each combination of strategies there may be several options available to the operator; and each involves phenomenological and operational considerations regarding uncertainty. Operational uncertainties include operator, system and instrument behavior during an accident. During the period September 26--28, 1990, a workshop was held at the University of California, Los Angeles, to address these uncertainties for Boiling Water Reactors (BWRs). This report contains a summary of the workshop proceedings.

  4. Accident Investigation of the October 1, 2013, Tice Electric...

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

    22, 2013 On October 2, 2013, at the request of the Bonneville Power Administration (BPA) Chief Safety Officer, a Level I Accident Investigation was convened to investigate an...

  5. Accident Investigation of the September 20, 2012 Fatal Fall from...

    Energy Savers [EERE]

    20, 2012 Fatal Fall from the Dworshak-Taft 1 Transmission Tower, at the Bonneville Power Marketing Administration Accident Investigation of the September 20, 2012 Fatal Fall...

  6. Type B Accident Investigation Report of the October 28, 2004...

    Office of Environmental Management (EM)

    of the October 28, 2004, Burn Injuries Sustained During an Office of Secure Transportation Joint Training Exercise at Fort Hunter-Liggett, CA Type B Accident Investigation Report...

  7. Type B Accident Investigation At Washington Closure Hanford,...

    Office of Environmental Management (EM)

    part of a Washington Closure Hanford, LLC (WCH) team of craft personnel preparing a bridge crane for removal from the 336 Building. Type B Accident Investigation At Washington...

  8. Type B Accident Investigation Board Report on the October 15...

    Office of Environmental Management (EM)

    Type B Accident Investigation Board Report on the October 15, 2001, Grout Injection Operator Injury at the Cold Test Pit South, Idaho National Engineering and Environmental...

  9. Type B Accident Investigation Board Report, May 8, 2004, Exothermic...

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

    August 17, 2004 On May 8, 2004, at approximately 11:00 am, an exothermic metal reaction (exothermic reaction) accident occurred during heating of surplus activated sodium shields...

  10. Estimating Pedestrian Accident Exposure: Automated Pedestrian Counting Devices Report

    E-Print Network [OSTI]

    Bu, Fanping; Greene-Roesel, Ryan; Diogenes, Mara Chagas; Ragland, David R

    2007-01-01

    pp. 283-291. Estimating Pedestrian Accident Exposure: Draftand J. Thiran. Counting Pedestrians in Video Sequences UsingPartnership (CLP) Automatic Pedestrian Counting Trial. Stage

  11. Type A Accident Investigation of the June 21, 2001, Drilling...

    Office of Environmental Management (EM)

    June 21, 2001, Drilling Rig Operator Injury at the Fermi National Accelerator Laboratory, August 2001 Type A Accident Investigation of the June 21, 2001, Drilling Rig Operator...

  12. Improvement of Design Codes to Account for Accident Thermal Effects...

    Office of Environmental Management (EM)

    IMPROVEMENT OF DESIGN CODES TO ACCOUNT FOR ACCIDENT THERMAL EFFECTS ON SEISMIC PERFORMANCE Amit H. Varma, Kadir Sener, Saahas Bhardwaj Purdue University Andrew Whittaker: Univ. of...

  13. Type B Accident Investigation Board Report of the Bechtel Jacobs...

    Office of Environmental Management (EM)

    Jacobs Company, LLC Employee Fall Injury on January 3, 2006, at the K-25 Building, East Tennessee Technology Park, Oak Ridge, Tennessee Type B Accident Investigation Board...

  14. Hazard Categorization and Accident Analysis Techniques for Compliance...

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

    Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports by Diane Johnson he purpose of this DOE Standard is to...

  15. Storage resource manager

    SciTech Connect (OSTI)

    Perelmutov, T.; Bakken, J.; Petravick, D.; /Fermilab

    2004-12-01

    Storage Resource Managers (SRMs) are middleware components whose function is to provide dynamic space allocation and file management on shared storage components on the Grid[1,2]. SRMs support protocol negotiation and reliable replication mechanism. The SRM standard supports independent SRM implementations, allowing for a uniform access to heterogeneous storage elements. SRMs allow site-specific policies at each location. Resource Reservations made through SRMs have limited lifetimes and allow for automatic collection of unused resources thus preventing clogging of storage systems with ''orphan'' files. At Fermilab, data handling systems use the SRM management interface to the dCache Distributed Disk Cache [5,6] and the Enstore Tape Storage System [15] as key components to satisfy current and future user requests [4]. The SAM project offers the SRM interface for its internal caches as well.

  16. Preliminary analysis of loss-of-coolant accident in Fukushima nuclear accident

    SciTech Connect (OSTI)

    Su'ud, Zaki; Anshari, Rio

    2012-06-06

    Loss-of-Coolant Accident (LOCA) in Boiling Water Reactor (BWR) especially on Fukushima Nuclear Accident will be discussed in this paper. The Tohoku earthquake triggered the shutdown of nuclear power reactors at Fukushima Nuclear Power station. Though shutdown process has been completely performed, cooling process, at much smaller level than in normal operation, is needed to remove decay heat from the reactor core until the reactor reach cold-shutdown condition. If LOCA happen at this condition, it will cause the increase of reactor fuel and other core temperatures and can lead to reactor core meltdown and exposure of radioactive material to the environment such as in the Fukushima Dai Ichi nuclear accident case. In this study numerical simulation has been performed to calculate pressure composition, water level and temperature distribution on reactor during this accident. There are two coolant regulating system that operational on reactor unit 1 at this accident, Isolation Condensers (IC) system and Safety Relief Valves (SRV) system. Average mass flow of steam to the IC system in this event is 10 kg/s and could keep reactor core from uncovered about 3,2 hours and fully uncovered in 4,7 hours later. There are two coolant regulating system at operational on reactor unit 2, Reactor Core Isolation Condenser (RCIC) System and Safety Relief Valves (SRV). Average mass flow of coolant that correspond this event is 20 kg/s and could keep reactor core from uncovered about 73 hours and fully uncovered in 75 hours later. There are three coolant regulating system at operational on reactor unit 3, Reactor Core Isolation Condenser (RCIC) system, High Pressure Coolant Injection (HPCI) system and Safety Relief Valves (SRV). Average mass flow of water that correspond this event is 15 kg/s and could keep reactor core from uncovered about 37 hours and fully uncovered in 40 hours later.

  17. ,"Underground Natural Gas Storage by Storage Type"

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

    Sourcekey","N5030US2","N5010US2","N5020US2","N5070US2","N5050US2","N5060US2" "Date","U.S. Natural Gas Underground Storage Volume (MMcf)","U.S. Total Natural Gas in Underground...

  18. Assessment of two BWR accident management strategies

    SciTech Connect (OSTI)

    Hodge, S.A.; Petek, M.

    1991-01-01

    Candidate mitigative strategies for management of in-vessel events during the late phase (after core degradation has occurred) of postulated BWR severe accidents were considered at Oak Ridge National Laboratory (ORNL) during 1990. The identification of new strategies was subject to the constraint that they should, to the maximum extent possible, make use of the existing equipment and water resources of the BWR facilities and not require major equipment modifications or additions. As a result of this effort, two of these candidate strategies were recommended for additional assessment. The first is a strategy for containment flooding to maintain the core and structural debris within the reactor vessel in the event that vessel injection cannot be restored to terminate a severe accident sequence. The second strategy pertains to the opposite case, for which vessel injection would be restored after control blade melting had begun; its purpose is to provide an injection source of borated water at the concentration necessary to preclude criticality upon recovering a damaged BWR core. Assessments of these two strategies have been performed during 1991 under the auspices of the Detailed Assessment of BWR In-Vessel Strategies Program. This paper provides a discussion of the motivation for and purpose of these strategies and the potential for their success. 33 refs., 9 figs.

  19. Material Selection for Accident Tolerant Fuel Cladding

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

    none,

    2014-07-01

    Alternative cladding materials are being investigated for accident tolerance, which can be defined as >100X improvement (compared to current Zr-based alloys) in oxidation resistance in steam environments at ?1200°C for short (?4 h) times. After reviewing a wide range of candidates, current steam oxidation testing is being conducted on Mo, MAX phases and FeCrAl alloys. Recently reported low mass losses for Mo in steam at 800°C could not be reproduced. Both FeCrAl and MAX phase Ti2AlC form a protective alumina scale in steam. However, commercial Ti2AlC that is not single phase, formed a much thicker oxide at 1200°C in steam and significant TiO2, and therefore may be challenging to use as a cladding or a coating. Alloy development for FeCrAl is seeking to maintain its steam oxidation resistance to 1475°C, while reducing its Cr content to minimize susceptibility to irradiation assisted Cr-rich ?’ formation. The composition effects and critical limits to retaining protective scale formation at >1400°C are still being evaluated. Keywords: Accident tolerant LWR Fuel cladding, FeCrAl, Mo, Ti2AlC, Al2O3, high temperature steam oxidation resistance

  20. Energy Storage | Clean Energy | ORNL

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

    Energy Storage SHARE Energy Storage Development Growing popularity and education about the benefits of alternative, sustainable transportation options-such as electric and hybrid...

  1. Secure Storage Architectures

    SciTech Connect (OSTI)

    Aderholdt, Ferrol; Caldwell, Blake A; Hicks, Susan Elaine; Koch, Scott M; Naughton, III, Thomas J; Pogge, James R; Scott, Stephen L; Shipman, Galen M; Sorrillo, Lawrence

    2015-01-01

    The purpose of this report is to clarify the challenges associated with storage for secure enclaves. The major focus areas for the report are: - review of relevant parallel filesystem technologies to identify assets and gaps; - review of filesystem isolation/protection mechanisms, to include native filesystem capabilities and auxiliary/layered techniques; - definition of storage architectures that can be used for customizable compute enclaves (i.e., clarification of use-cases that must be supported for shared storage scenarios); - investigate vendor products related to secure storage. This study provides technical details on the storage and filesystem used for HPC with particular attention on elements that contribute to creating secure storage. We outline the pieces for a a shared storage architecture that balances protection and performance by leveraging the isolation capabilities available in filesystems and virtualization technologies to maintain the integrity of the data. Key Points: There are a few existing and in-progress protection features in Lustre related to secure storage, which are discussed in (Chapter 3.1). These include authentication capabilities like GSSAPI/Kerberos and the in-progress work for GSSAPI/Host-keys. The GPFS filesystem provides native support for encryption, which is not directly available in Lustre. Additionally, GPFS includes authentication/authorization mechanisms for inter-cluster sharing of filesystems (Chapter 3.2). The limitations of key importance for secure storage/filesystems are: (i) restricting sub-tree mounts for parallel filesystem (which is not directly supported in Lustre or GPFS), and (ii) segregation of hosts on the storage network and practical complications with dynamic additions to the storage network, e.g., LNET. A challenge for VM based use cases will be to provide efficient IO forwarding of the parallel filessytem from the host to the guest (VM). There are promising options like para-virtualized filesystems to help with this issue, which are a particular instances of the more general challenge of efficient host/guest IO that is the focus of interfaces like virtio. A collection of bridging technologies have been identified in Chapter 4, which can be helpful to overcome the limitations and challenges of supporting efficient storage for secure enclaves. The synthesis of native filesystem security mechanisms and bridging technologies led to an isolation-centric storage architecture that is proposed in Chapter 5, which leverages isolation mechanisms from different layers to facilitate secure storage for an enclave. Recommendations: The following highlights recommendations from the investigations done thus far. - The Lustre filesystem offers excellent performance but does not support some security related features, e.g., encryption, that are included in GPFS. If encryption is of paramount importance, then GPFS may be a more suitable choice. - There are several possible Lustre related enhancements that may provide functionality of use for secure-enclaves. However, since these features are not currently integrated, the use of Lustre as a secure storage system may require more direct involvement (support). (*The network that connects the storage subsystem and users, e.g., Lustre s LNET.) - The use of OpenStack with GPFS will be more streamlined than with Lustre, as there are available drivers for GPFS. - The Manilla project offers Filesystem as a Service for OpenStack and is worth further investigation. Manilla has some support for GPFS. - The proposed Lustre enhancement of Dynamic-LNET should be further investigated to provide more dynamic changes to the storage network which could be used to isolate hosts and their tenants. - The Linux namespaces offer a good solution for creating efficient restrictions to shared HPC filesystems. However, we still need to conduct a thorough round of storage/filesystem benchmarks. - Vendor products should be more closely reviewed, possibly to include evaluation of performance/protection of select products. (Note, we are investigation the opti

  2. LIQUID PROPANE GAS (LPG) STORAGE AREA BOILING LIQUID EXPANDING VAPOR EXPLOSION (BLEVE) ANALYSIS

    SciTech Connect (OSTI)

    PACE, M.E.

    2004-01-13

    The PHA and the FHAs for the SWOC MDSA (HNF-14741) identified multiple accident scenarios in which vehicles powered by flammable gases (e.g., propane), or combustible or flammable liquids (e.g., gasoline, LPG) are involved in accidents that result in an unconfined vapor cloud explosion (UVCE) or in a boiling liquid expanding vapor explosion (BLEVE), respectively. These accident scenarios are binned in the Bridge document as FIR-9 scenarios. They are postulated to occur in any of the MDSA facilities. The LPG storage area will be in the southeast corner of CWC that is relatively remote from store distaged MAR. The location is approximately 30 feet south of MO-289 and 250 feet east of 2401-W by CWC Gate 10 in a large staging area for unused pallets and equipment.

  3. Ultrafine hydrogen storage powders

    DOE Patents [OSTI]

    Anderson, Iver E. (Ames, IA); Ellis, Timothy W. (Doylestown, PA); Pecharsky, Vitalij K. (Ames, IA); Ting, Jason (Ames, IA); Terpstra, Robert (Ames, IA); Bowman, Robert C. (La Mesa, CA); Witham, Charles K. (Pasadena, CA); Fultz, Brent T. (Pasadena, CA); Bugga, Ratnakumar V. (Arcadia, CA)

    2000-06-13

    A method of making hydrogen storage powder resistant to fracture in service involves forming a melt having the appropriate composition for the hydrogen storage material, such, for example, LaNi.sub.5 and other AB.sub.5 type materials and AB.sub.5+x materials, where x is from about -2.5 to about +2.5, including x=0, and the melt is gas atomized under conditions of melt temperature and atomizing gas pressure to form generally spherical powder particles. The hydrogen storage powder exhibits improved chemcial homogeneity as a result of rapid solidfication from the melt and small particle size that is more resistant to microcracking during hydrogen absorption/desorption cycling. A hydrogen storage component, such as an electrode for a battery or electrochemical fuel cell, made from the gas atomized hydrogen storage material is resistant to hydrogen degradation upon hydrogen absorption/desorption that occurs for example, during charging/discharging of a battery. Such hydrogen storage components can be made by consolidating and optionally sintering the gas atomized hydrogen storage powder or alternately by shaping the gas atomized powder and a suitable binder to a desired configuration in a mold or die.

  4. Web Based Course: SAF-230DE, Accident Investigation Overview Promotional Video

    Broader source: Energy.gov [DOE]

    This course that provides an overview of the fundamentals of accident investigation. The course is intended to meet the every five year refresher training requirement for DOE Federal Accident Investigators under DOE O 225.1B, Accident Investigations.

  5. OFFICE OF RISK MANAGEMENT STUDENT ACCIDENT INVESTIGATION REPORT

    E-Print Network [OSTI]

    Arnold, Elizabeth A.

    OFFICE OF RISK MANAGEMENT STUDENT ACCIDENT INVESTIGATION REPORT James Madison University, Office of Risk Management, 131 West Grace Street, MSC 6703 Harrisonburg, VA 22807, Phone: 540-568-7812, Fax: 540/Injury: Student's Signature: Date: Return Original Form to: #12;OFFICE OF RISK MANAGEMENT STUDENT ACCIDENT

  6. Cold Vacuum Drying (CVD) Facility Design Basis Accident Analysis Documentation

    SciTech Connect (OSTI)

    PIEPHO, M.G.

    1999-10-20

    This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report, ''Cold Vacuum Drying Facility Final Safety Analysis Report (FSAR).'' All assumptions, parameters and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR.

  7. BWR containment failure analysis during degraded-core accidents

    SciTech Connect (OSTI)

    Yue, D.D.

    1982-06-06

    This paper presents a containment failure mode analysis during a spectrum of postulated degraded core accident sequences in a typical 1000-MW(e) boiling water reactor (BWR) with a Mark-I wetwell containment. Overtemperature failure of containment electric penetration assemblies (CEPAs) has been found to be the major failure mode during such accidents.

  8. Storage Exchange: A Global Trading Platform for Storage Services

    E-Print Network [OSTI]

    Melbourne, University of

    Storage Exchange: A Global Trading Platform for Storage Services Martin Placek and Rajkumar Buyya}@csse.unimelb.edu.au Abstract. The Storage Exchange (SX) is a new platform allowing stor- age to be treated as a tradeable resource. Organisations with varying storage requirements can use the SX platform to trade and exchange

  9. Building Trust in Storage Outsourcing: Secure Accounting of Utility Storage

    E-Print Network [OSTI]

    Minnesota, University of

    Building Trust in Storage Outsourcing: Secure Accounting of Utility Storage Vishal Kher Yongdae Kim are witnessing a revival of Storage Service Providers (SSP) in the form of new vendors as well as traditional players. While storage outsourcing is cost-effective, many companies are hesitating to outsource

  10. Storage Exchange: A Global Trading Platform for Storage Services

    E-Print Network [OSTI]

    Melbourne, University of

    Storage Exchange: A Global Trading Platform for Storage Services Martin Placek and Rajkumar Buyya,raj}@csse.unimelb.edu.au Abstract. The Storage Exchange (SX) is a new platform allowing stor- age to be treated as a tradeable resource. Organisations with varying storage requirements can use the SX platform to trade and exchange

  11. Regulatory Concerns on the In-Containment Water Storage System of the Korean Next Generation Reactor

    SciTech Connect (OSTI)

    Ahn, Hyung-Joon; Lee, Jae-Hun; Bang, Young-Seok; Kim, Hho-Jung

    2002-07-15

    The in-containment water storage system (IWSS) is a newly adopted system in the design of the Korean Next Generation Reactor (KNGR). It consists of the in-containment refueling water storage tank, holdup volume tank, and cavity flooding system (CFS). The IWSS has the function of steam condensation and heat sink for the steam release from the pressurizer and provides cooling water to the safety injection system and containment spray system in an accident condition and to the CFS in a severe accident condition. With the progress of the KNGR design, the Korea Institute of Nuclear Safety has been developing Safety and Regulatory Requirements and Guidances for safety review of the KNGR. In this paper, regarding the IWSS of the KNGR, the major contents of the General Safety Criteria, Specific Safety Requirements, Safety Regulatory Guides, and Safety Review Procedures were introduced, and the safety review items that have to be reviewed in-depth from the regulatory viewpoint were also identified.

  12. Safety Aspects of Dry Spent Fuel Storage and Spent Fuel Management - 13559

    SciTech Connect (OSTI)

    Botsch, W.; Smalian, S.; Hinterding, P.

    2013-07-01

    Dry storage systems are characterized by passive and inherent safety systems ensuring safety even in case of severe incidents or accidents. After the events of Fukushima, the advantages of such passively and inherently safe dry storage systems have become more and more obvious. As with the storage of all radioactive materials, the storage of spent nuclear fuel (SF) and high-level radioactive waste (HLW) must conform to safety requirements. Following safety aspects must be achieved throughout the storage period: - safe enclosure of radioactive materials, - safe removal of decay heat, - securing nuclear criticality safety, - avoidance of unnecessary radiation exposure. The implementation of these safety requirements can be achieved by dry storage of SF and HLW in casks as well as in other systems such as dry vault storage systems or spent fuel pools, where the latter is neither a dry nor a passive system. Furthermore, transport capability must be guaranteed during and after storage as well as limitation and control of radiation exposure. The safe enclosure of radioactive materials in dry storage casks can be achieved by a double-lid sealing system with surveillance of the sealing system. The safe removal of decay heat must be ensured by the design of the storage containers and the storage facility. The safe confinement of radioactive inventory has to be ensured by mechanical integrity of fuel assembly structures. This is guaranteed, e.g. by maintaining the mechanical integrity of the fuel rods or by additional safety measures for defective fuel rods. In order to ensure nuclear critically safety, possible effects of accidents have also to be taken into consideration. In case of dry storage it might be necessary to exclude the re-positioning of fissile material inside the container and/or neutron moderator exclusion might be taken into account. Unnecessary radiation exposure can be avoided by the cask or canister vault system itself. In Germany dry storage of SF in casks fulfills both transport and storage requirements. Mostly, storage facilities are designed as concrete buildings above the ground, but due to regional constraints, one storage facility has also been built as a rock tunnel. The decay heat is always removed by natural air flow; further technical equipment is not needed. The removal of decay heat and shielding had been modeled and calculated by state-of-the-art computer codes before such a facility has been built. TueV and BAM present their long experience in the licensing process for sites and casks and inform about spent nuclear fuel management and issues concerning dry storage of spent nuclear fuel. Different storage systems and facilities in Germany, Europe and world-wide are compared with respect to the safety aspects mentioned above. Initial points are the safety issues of wet storage of SF, and it is shown how dry storage systems can ensure the compliance with the mentioned safety criteria over a long storage period. The German storage concept for dry storage of SF and HLW is presented and discussed. Exemplarily, the process of licensing, erection and operation of selected German dry storage facilities is presented. (authors)

  13. Microsoft Word - 2015.06.22 - Report to Congress - Accident Tolerant...

    Energy Savers [EERE]

    OF LWR FUELS WITH ENHANCED ACCIDENT TOLERANCE Page i Development of Light Water Reactor Fuels with Enhanced Accident Tolerance Report to Congress April 2015 United States...

  14. Hemodynamic Monitoring TRANSTHORACIC LINES

    E-Print Network [OSTI]

    Kay, Mark A.

    and with position changes. 5. All lines should have either heparinized saline or D5W infusing. 6. Avoid infusing the line. 9. Never use LA for infusions or bolus medications. 10. Vigilant observation for AIR. B. Line

  15. APS Storage Ring Parameters

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

    next up previous Next: Main Parameters APS Storage Ring Parameters M. Borland, G. Decker, L. Emery, W. Guo, K. Harkay, V. Sajaev, C.-Y. Yao Advanced Photon Source September 8, 2010...

  16. Thermal Energy Storage

    SciTech Connect (OSTI)

    Rutberg, Michael; Hastbacka, Mildred; Cooperman, Alissa; Bouza, Antonio

    2013-06-05

    The article discusses thermal energy storage technologies. This article addresses benefits of TES at both the building site and the electricity generation source. The energy savings and market potential of thermal energy store are reviewed as well.

  17. Hydrogen storage compositions

    DOE Patents [OSTI]

    Li, Wen; Vajo, John J.; Cumberland, Robert W.; Liu, Ping

    2011-04-19

    Compositions for hydrogen storage and methods of making such compositions employ an alloy that exhibits reversible formation/deformation of BH.sub.4.sup.- anions. The composition includes a ternary alloy including magnesium, boron and a metal and a metal hydride. The ternary alloy and the metal hydride are present in an amount sufficient to render the composition capable of hydrogen storage. The molar ratio of the metal to magnesium and boron in the alloy is such that the alloy exhibits reversible formation/deformation of BH.sub.4.sup.- anions. The hydrogen storage composition is prepared by combining magnesium, boron and a metal to prepare a ternary alloy and combining the ternary alloy with a metal hydride to form the hydrogen storage composition.

  18. Wet storage integrity update

    SciTech Connect (OSTI)

    Bailey, W.J.; Johnson, A.B. Jr.

    1983-09-01

    This report includes information from various studies performed under the Wet Storage Task of the Spent Fuel Integrity Project of the Commercial Spent Fuel Management (CSFM) Program at Pacific Northwest Laboratory. An overview of recent developments in the technology of wet storage of spent water reactor fuel is presented. Licensee Event Reports pertaining to spent fuel pools and the associated performance of spent fuel and storage components during wet storage are discussed. The current status of fuel that was examined under the CSFM Program is described. Assessments of the effect of boric acid in spent fuel pool water on the corrosion and stress corrosion cracking of stainless steel and the stress corrosion cracking of stainless steel piping containing stagnant water at spent fuel pools are discussed. A list of pertinent publications is included. 84 references, 21 figures, 11 tables.

  19. Analog storage integrated circuit

    DOE Patents [OSTI]

    Walker, J.T.; Larsen, R.S.; Shapiro, S.L.

    1989-03-07

    A high speed data storage array is defined utilizing a unique cell design for high speed sampling of a rapidly changing signal. Each cell of the array includes two input gates between the signal input and a storage capacitor. The gates are controlled by a high speed row clock and low speed column clock so that the instantaneous analog value of the signal is only sampled and stored by each cell on coincidence of the two clocks. 6 figs.

  20. Analog storage integrated circuit

    DOE Patents [OSTI]

    Walker, J. T. (Palo Alto, CA); Larsen, R. S. (Menlo Park, CA); Shapiro, S. L. (Palo Alto, CA)

    1989-01-01

    A high speed data storage array is defined utilizing a unique cell design for high speed sampling of a rapidly changing signal. Each cell of the array includes two input gates between the signal input and a storage capacitor. The gates are controlled by a high speed row clock and low speed column clock so that the instantaneous analog value of the signal is only sampled and stored by each cell on coincidence of the two clocks.

  1. Marketing Cool Storage Technology 

    E-Print Network [OSTI]

    McCannon, L.

    1987-01-01

    -09-74 Proceedings from the Ninth Annual Industrial Energy Technology Conference, Houston, TX, September 16-18, 1987 Utility Cool Storage Inducement Progra~ ,.,.. ?? ,.. ,., Utilities With Inducement~ CA -- Southern California Edison San Diego Gas &Electric..., electric utilities have been faced with risin~ construction costs, more strin~ent re~ulations, and increasin~ environmental constraints re~ardin~ development of new generatin~ facilities. As the viability of cool storage has been substantiated. bv...

  2. MELCOR accident analysis for ARIES-ACT

    SciTech Connect (OSTI)

    Paul W. Humrickhouse; Brad J. Merrill

    2012-08-01

    We model a loss of flow accident (LOFA) in the ARIES-ACT1 tokamak design. ARIES-ACT1 features an advanced SiC blanket with LiPb as coolant and breeder, a helium cooled steel structural ring and tungsten divertors, a thin-walled, helium cooled vacuum vessel, and a room temperature water-cooled shield outside the vacuum vessel. The water heat transfer system is designed to remove heat by natural circulation during a LOFA. The MELCOR model uses time-dependent decay heats for each component determined by 1-D modeling. The MELCOR model shows that, despite periodic boiling of the water coolant, that structures are kept adequately cool by the passive safety system.

  3. Big Rock Point severe accident management strategies

    SciTech Connect (OSTI)

    Brogan, B.A. [Consumers Power Co., Charlevoix, MI (United States); Gabor, J.R. [Dames and Moore, Westmont, IL (United States)

    1996-07-01

    December 1994, the Nuclear Energy Institute (NEI) issued guidance relative to the formal industry position on Severe Accident Management (SAM) approved by the NEI Strategic Issues Advisory Committee on November 4, 1994. This paper summarizes how Big Rock Point (BRP) has and continues to address SAM strategies. The historical accounting portion of this presentation includes a description of how the following projects identified and defined the current Big Rock Point SAM strategies: the 1981 Level 3 Probabilistic Risk Assessment performance; the development of the Plant Specific Technical Guidelines from which the symptom oriented Emergency Operating Procedures (EOPs) were developed; the Control Room Design Review; and, the recent completion of the Individual Plant Evaluation (IPE). In addition to the historical presentation deliberation, this paper the present activities that continue to stress SAM strategies.

  4. Guidelines for accident prevention and emergency preparedness

    SciTech Connect (OSTI)

    Fthenakis, V.M.; Morris, S.C.; Moskowitz, P.D.

    1993-05-01

    This report reviews recent developments in the guidelines on chemical accident prevention, risk assessment, and management of chemical emergencies, principally in the United States and Europe, and discusses aspects of their application to developing countries. Such guidelines are either in the form of laws or regulations promulgated by governments, or of recommendations from international, professional, or non governmental organizations. In many cases, these guidelines specify lists of materials of concern and methods for evaluating safe usage of these materials and recommend areas of responsibility for different organizations; procedures to be included in planning, evaluation, and response; and appropriate levels of training for different classes of workers. Guidelines frequently address the right of communities to be informed of potential hazards and address ways for them to participate in planning and decision making.

  5. Storage In C Matt Bishop

    E-Print Network [OSTI]

    Bishop, Matt

    Storage In C Matt Bishop Research Institute for Advanced Computer Science NASA Ames Research Center. Intimately bound with the idea of scope is that of storage. When a program deÞnes a variable, the compiler storage (such as on a stack) or as more permanent storage (in data space.) Recall that the format of a C

  6. Storage In C Matt Bishop

    E-Print Network [OSTI]

    Bishop, Matt

    Storage In C Matt Bishop Research Institute for Advanced Computer Science NASA Ames Research Center. Intimately bound with the idea of scope is that of storage. When a program defines a variable, the compiler storage (such as on a stack) or as more permanent storage (in data space.) Recall that the format of a C

  7. Savannah River Hydrogen Storage Technology

    Broader source: Energy.gov [DOE]

    Presentation from the Hydrogen Storage Pre-Solicitation Meeting held June 19, 2003 in Washington, DC.

  8. Graphite Oxidation Simulation in HTR Accident Conditions

    SciTech Connect (OSTI)

    El-Genk, Mohamed

    2012-10-19

    Massive air and water ingress, following a pipe break or leak in steam-generator tubes, is a design-basis accident for high-temperature reactors (HTRs). Analysis of these accidents in both prismatic and pebble bed HTRs requires state-of-the-art capability for predictions of: 1) oxidation kinetics, 2) air ?helium gas mixture stratification and diffusion into the core following the depressurization, 3) transport of multi-species gas mixture, and 4) graphite corrosion. This project will develop a multi-dimensional, comprehensive oxidation kinetics model of graphite in HTRs, with diverse capabilities for handling different flow regimes. The chemical kinetics/multi-species transport model for graphite burning and oxidation will account for temperature-related changes in the properties of graphite, oxidants (O2, H2O, CO), reaction products (CO, CO2, H2, CH4) and other gases in the mixture (He and N2). The model will treat the oxidation and corrosion of graphite in geometries representative of HTR core component at temperatures of 900°C or higher. The developed chemical reaction kinetics model will be user-friendly for coupling to full core analysis codes such as MELCOR and RELAP, as well as computational fluid dynamics (CFD) codes such as CD-adapco. The research team will solve governing equations for the multi-dimensional flow and the chemical reactions and kinetics using Simulink, an extension of the MATLAB solver, and will validate and benchmark the model's predictions using reported experimental data. Researchers will develop an interface to couple the validated model to a commercially available CFD fluid flow and thermal-hydraulic model of the reactor , and will perform a simulation of a pipe break in a prismatic core HTR, with the potential for future application to a pebble-bed type HTR.

  9. Concentrating Solar Program; Session: Thermal Storage - Overview (Presentation)

    SciTech Connect (OSTI)

    Glatzmaier, G.; Mehos, M.; Mancini, T.

    2008-04-01

    The project overview of this presentation is: (1) description--(a) laboratory R and D in advanced heat transfer fluids (HTF) and thermal storage systems; (b) FOA activities in solar collector and component development for use of molten salt as a heat transfer and storage fluid; (c) applications for all activities include line focus and point focus solar concentrating technologies; (2) Major FY08 Activities--(a) advanced HTF development with novel molten salt compositions with low freezing temperatures, nanofluids molecular modeling and experimental studies, and use with molten salt HTF in solar collector field; (b) thermal storage systems--cost analysis and updates for 2-tank and thermocline storage and model development and analysis to support near-term trought deployment; (c) thermal storage components--facility upgrade to support molten salt component testing for freeze-thaw receiver testing, long-shafted molten salt pump for parabolic trough and power tower thermal storage systems; (d) CSP FOA support--testing and evaluation support for molten salt component and field testing work, advanced fluids and storage solicitation preparation, and proposal evaluation for new advanced HTF and thermal storage FOA.

  10. DOE Global Energy Storage Database

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    The DOE International Energy Storage Database has more than 400 documented energy storage projects from 34 countries around the world. The database provides free, up-to-date information on grid-connected energy storage projects and relevant state and federal policies. More than 50 energy storage technologies are represented worldwide, including multiple battery technologies, compressed air energy storage, flywheels, gravel energy storage, hydrogen energy storage, pumped hydroelectric, superconducting magnetic energy storage, and thermal energy storage. The policy section of the database shows 18 federal and state policies addressing grid-connected energy storage, from rules and regulations to tariffs and other financial incentives. It is funded through DOE’s Sandia National Laboratories, and has been operating since January 2012.

  11. Storage monitoring systems for the year 2000

    SciTech Connect (OSTI)

    Nilsen, C.; Pollock, R.

    1997-12-31

    In September 1993, President Clinton stated the US would ensure that its fissile material meet the highest standards of safety, security, and international accountability. Frequent human inspection of the material could be used to ensure these standards. However, it may be more effective and less expensive to replace these manual inspections with virtual inspections via remote monitoring technologies. To prepare for this future, Sandia National Laboratories has developed several monitoring systems, including the Modular Integrated Monitoring System (MIMS) and Project Straight-Line. The purpose of this paper is to describe a Sandia effort that merges remote monitoring technologies into a comprehensive storage monitoring system that will meet the near-term as well as the long-term requirements for these types of systems. Topics discussed include: motivations for storage monitoring systems to include remote monitoring; an overview of the needs and challenges of providing a storage monitoring system for the year 2000; an overview of how the MIMS and Straight-Line can be enhanced so that together they create an integrated and synergistic information system by the end of 1997; and suggested milestones for 1998 and 1999 to assure steady progress in preparing for the needs of 2000.

  12. Accident management then and now: Progress since Di Salvo's work

    SciTech Connect (OSTI)

    Shotkin, L.M.

    1991-01-01

    The nuclear industry is now initiating a serious effort to define the elements of an accident management program at each utility with an operating reactor, which is a significant change in conditions from those in 1985, when the work of Di Salvo et al. was published. Each utility is now conducting an individual plant examination (IPE) to uncover plant vulnerabilities to severe accidents. In conjunction with the IPE program, the Nuclear Utility Management and Resources committee, the Electric Power Research Institute, and owners' groups are developing an accident management program. This program is emphasizing the management program. This program is emphasizing the management of severe accidents (i.e., accidents that proceed to significant core melt) including strategies for managing ex-vessel events. Attention is also being paid to interfacing any severe accident management strategies with existing emergency operating procedures already in place at utilities. The industry program is addressing the five elements define by the US Nuclear Regulatory Commission (NRC): (1) strategies; (2) instrumentation; (3) guidance and computational aids; (4) organization and decision making; and (5) training. It will also be able to accept new information as it becomes available from ongoing efforts to better understand severe accidents and how to manage them effectively.

  13. Plains and Eastern Clean Line Transmission Line: Comment from...

    Energy Savers [EERE]

    Plains and Eastern Clean Line Transmission Line: Comment from Marshall Hughes Plains and Eastern Clean Line Transmission Line: Comment from Marshall Hughes Comment submitted on...

  14. Plains and Eastern Clean Line Transmission Line: Comment from...

    Office of Environmental Management (EM)

    from Block Plains and Eastern Clean Line: Arkansas and Oklahoma Plains and Eastern Clean Line Transmission Line: Comment from Block Plains and Eastern Clean Line: Arkansas and...

  15. BALLISTICS TESTING OF THE 9977 SHIPPING PACKAGE FOR STORAGE APPLICATIONS

    SciTech Connect (OSTI)

    Loftin, B.; Abramczyk, G.; Koenig, R.

    2012-06-06

    Radioactive materials are stored in a variety of locations throughout the DOE complex. At the Savannah River Site (SRS), materials are stored within dedicated facilities. Each of those facilities has a documented safety analysis (DSA) that describes accidents that the facility and the materials within it may encounter. Facilities at the SRS are planning on utilizing the certified Model 9977 Shipping Package as a long term storage package and one of these facilities required ballistics testing. Specifically, in order to meet the facility DSA, the radioactive materials (RAM) must be contained within the storage package after impact by a .223 caliber round. In order to qualify the Model 9977 Shipping Package for storage in this location, the package had to be tested under these conditions. Over the past two years, the Model 9977 Shipping Package has been subjected to a series of ballistics tests. The purpose of the testing was to determine if the 9977 would be suitable for use as a storage package at a Savannah River Site facility. The facility requirements are that the package must not release any of its contents following the impact in its most vulnerable location by a .223 caliber round. A package, assembled to meet all of the design requirements for a certified 9977 shipping configuration and using simulated contents, was tested at the Savannah River Site in March of 2011. The testing was completed and the package was examined. The results of the testing and examination are presented in this paper.

  16. Characteristics and Behaviour of High Burnup Fuel that May Affect the Containment Source Terms for Cask Accidents

    SciTech Connect (OSTI)

    Einziger, Robert E.; Beyer, Carl E.

    2007-08-01

    Current risk assessments of spent fuel in storage and transportation casks use the properties of LWR fuel below 45 GWd/MTU. Fuel is being driven to higher burnups that may influence the source term in cask accidents. To achieve these burnups the manufacturers are introducing new assembly designs and cladding alloys. As a result, at the higher burnups (? 50 GWd/MTU) some of the characteristics of the fuel pellets, cladding, and assembly design used in the safety analysis have changed. The fuel pellet has developed a fine grained, Pu rich rim zone on its exterior surface. The source term may increase by 1 – 3 orders of magnitude depending on the fracture characteristics of the rim. The cladding may acquire hydrogen contents up to 700 wppm during the increased exposure. Embrittlement with subsequent lose of ductility may occur, especially if there is hydride reorientation. As a result, there may be a greater propensity for fracture of the rods upon impact with subsequent release of fuel particulate and gas. Significantly improved source terms can be developed if additional data on fuel rim fracture as a function of impact energy, the dependence of cladding ductility for Zircaloy and the newer cladding alloys as a function of hydride reorientation, and release characteristics for fractured rods were obtained. CRUD spallation characteristics only make a significant contribution to the source term if the rods do not fracture in the accident or if a fire only accident occurs.

  17. Post-accident inhalation exposure and experience with plutonium

    SciTech Connect (OSTI)

    Shinn, J

    1998-06-01

    This paper addresses the issue of inhalation exposure immediately afterward and for a long time following a nuclear accident. For the cases where either a nuclear weapon burns or explodes prior to nuclear fission, or at locations close to a nuclear reactor accident containing fission products, a major concern is the inhalation of aerosolized plutonium (Pu) particles producing alpha-radiation. We have conducted field studies of Pu- contaminated real and simulated accident sites at Bikini, Johnston Atoll, Tonopah (Nevada), Palomares (Spain), Chernobyl, and Maralinga (Australia).

  18. Radioactive waste storage issues

    SciTech Connect (OSTI)

    Kunz, D.E.

    1994-08-15

    In the United States we generate greater than 500 million tons of toxic waste per year which pose a threat to human health and the environment. Some of the most toxic of these wastes are those that are radioactively contaminated. This thesis explores the need for permanent disposal facilities to isolate radioactive waste materials that are being stored temporarily, and therefore potentially unsafely, at generating facilities. Because of current controversies involving the interstate transfer of toxic waste, more states are restricting the flow of wastes into - their borders with the resultant outcome of requiring the management (storage and disposal) of wastes generated solely within a state`s boundary to remain there. The purpose of this project is to study nuclear waste storage issues and public perceptions of this important matter. Temporary storage at generating facilities is a cause for safety concerns and underscores, the need for the opening of permanent disposal sites. Political controversies and public concern are forcing states to look within their own borders to find solutions to this difficult problem. Permanent disposal or retrievable storage for radioactive waste may become a necessity in the near future in Colorado. Suitable areas that could support - a nuclear storage/disposal site need to be explored to make certain the health, safety and environment of our citizens now, and that of future generations, will be protected.

  19. Energy storage connection system

    DOE Patents [OSTI]

    Benedict, Eric L.; Borland, Nicholas P.; Dale, Magdelena; Freeman, Belvin; Kite, Kim A.; Petter, Jeffrey K.; Taylor, Brendan F.

    2012-07-03

    A power system for connecting a variable voltage power source, such as a power controller, with a plurality of energy storage devices, at least two of which have a different initial voltage than the output voltage of the variable voltage power source. The power system includes a controller that increases the output voltage of the variable voltage power source. When such output voltage is substantially equal to the initial voltage of a first one of the energy storage devices, the controller sends a signal that causes a switch to connect the variable voltage power source with the first one of the energy storage devices. The controller then causes the output voltage of the variable voltage power source to continue increasing. When the output voltage is substantially equal to the initial voltage of a second one of the energy storage devices, the controller sends a signal that causes a switch to connect the variable voltage power source with the second one of the energy storage devices.

  20. The Accident at Fukushima: What Happened?

    SciTech Connect (OSTI)

    Fujie, Takao

    2012-07-01

    At 2:46 PM, on the coast of the Pacific Ocean in eastern Japan, people were spending an ordinary afternoon. The earthquake had a magnitude of 9.0, the fourth largest ever recorded in the world. Avery large number of aftershocks were felt after the initial earthquake. More than 100 of them had a magnitude of over 6.0. There were very few injured or dead at this point. The large earthquake caused by this enormous crustal deformation spawned a rare and enormous tsunami that crashed down 30-40 minutes later. It easily cleared the high levees, washing away cars and houses and swallowing buildings of up to three stories in height. The largest tsunami reading taken from all regions was 40 meters in height. This tsunami reached the West Coast of the United States and the Pacific coast of South America, with wave heights of over two meters. It was due to this tsunami that the disaster became one of a not imaginable scale, which saw the number of dead or missing reach about 20,000 persons. The enormous tsunami headed for 15 nuclear power plants on the Pacific coast, but 11 power plants withstood the tsunami and attained cold shutdown. The flood height of the tsunami that struck each power station ranged to a maximum of 15 meters. The Fukushima Daiichi Nuclear Power Plant Units experienced the largest and the cores of three reactors suffered meltdown. As a result, more than 160,000 residents were forced to evacuate, and are still living in temporary accommodation. The main focus of this presentation is on what happened at the Fukushima Daiichi, and how station personnel responded to the accident, with considerable international support. A year after the Fukushima Daiichi accident, Japan is in the process of leveraging the lessons learned from the accident to further improve the safety of nuclear power facilities and regain the trust of society. In this connection, not only international organizations, including IAEA, and WANO, but also governmental organizations and nuclear industry representatives from various countries, have been evaluating what happened at Fukushima Daiichi. Support from many countries has contributed to successfully stabilizing the Fukushima Daiichi Nuclear Power Station. International cooperation is required as Japan started along the long road to decommissioning the reactors. Such cooperation with the international community would achieve the decommissioning of the damaged reactors. Finally, recovery plans by the Japanese government to decontaminate surrounding regions have been started in order to get residents back to their homes as early as possible. Looking at the world's nuclear power industry, there are currently approximately 440 reactors in operation and 60 under construction. Despite the dramatic consequences of the Fukushima Daiichi catastrophe it is expected that the importance of nuclear power generation will not change in the years to come. Newly accumulated knowledge and capabilities must be passed on to the next generation. This is the duty put upon us and which is one that we must embrace.

  1. Storage battery systems analysis

    SciTech Connect (OSTI)

    Murphy, K.D.

    1982-01-01

    Storage Battery Systems Analysis supports the battery Exploratory Technology Development and Testing Project with technical and economic analysis of battery systems in various end-use applications. Computer modeling and simulation techniques are used in the analyses. Analysis objectives are achieved through both in-house efforts and outside contracts. In-house studies during FY82 included a study of the relationship between storage battery system reliability and cost, through cost-of-investment and cost-of-service interruption inputs; revision and update of the SOLSTOR computer code in standard FORTRAN 77 form; parametric studies of residential stand-alone photovoltaic systems using the SOLSTOR code; simulation of wind turbine collector/storage battery systems for the community of Kalaupapa, Molokai, Hawaii.

  2. Type B Accident Investigation Board Report of the Savannah River...

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

    Savannah River Site Hand Injury at the Salt Waste Processing Facility on October 6, 2009 Type B Accident Investigation Board Report of the Savannah River Site Hand Injury at the...

  3. Accident Investigation of the February 5, 2014, Underground Salt...

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

    5, 2014, Underground Salt Haul Truck Fire at the Waste Isolation Pilot Plant, Carlsbad NM Accident Investigation of the February 5, 2014, Underground Salt Haul Truck Fire at the...

  4. Type B Accident Investigation of the Savannah River Site Arc...

    Energy Savers [EERE]

    H2 Demolition, in Niskayuna, New, York Type B Accident Investigation Board Report of the Savannah River Site Hand Injury at the Salt Waste Processing Facility on October 6, 2009...

  5. Type B Accident Investigation of the Arc Flash at Brookhaven...

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

    event and causal factor analysis. Type B Accident Investigation of the Arc Flash at Brookhaven National Laboratory, April 14, 2006 More Documents & Publications DOE-HDBK-1092-1998...

  6. Type B Accident Investigation of the January 10, 2006, Flash...

    Energy Savers [EERE]

    Review, Savannah River National Laboratory - January 2012 Type B Accident Investigation of the Arc Flash at Brookhaven National Laboratory, April 14, 2006 Audit Report: OAS-L-06-15...

  7. Accidents, engineering and history at NASA: 1967-2003

    E-Print Network [OSTI]

    Brown, Alexander F. G. (Alexander Frederic Garder), 1970-

    2009-01-01

    The manned spaceflight program of the National Aeronautics and Space Administration (NASA) has suffered three fatal accidents: one in the Apollo program and two in the Space Transportation System (the Shuttle). These were ...

  8. Type B Accident Investigation of the Acid Vapor Inhalation on...

    Energy Savers [EERE]

    of the Acid Vapor Inhalation on June 7, 2005, in TA-48, Building RC-1 Room 402 at the Los Alamos National Laboratory Type B Accident Investigation of the Acid Vapor Inhalation on...

  9. The Effect of Removing Accidents Repeaters From the Road

    E-Print Network [OSTI]

    Ferreira, Joseph Jr.

    In newspaper editorials, public commentaries and the like, licensing authorities are often advised to solve the "accident problem" by taking the "nut behind the wheel" off the road. This paper uses six-year driver records ...

  10. Failsafe : living with man-made disaster and accident

    E-Print Network [OSTI]

    Higgins, Saoirse, 1966-

    2004-01-01

    "There is no progress with out progress of the catastrophe." Virilio. This thesis project proposes that technological solutions in the design of our systems are not enough to prevent 'man-made' accident. Social, organisational ...

  11. The 2011 Tohoku earthquake, tsunami, and Fukushima nuclear accident

    E-Print Network [OSTI]

    Ferrari, Silvia

    The 2011 Tohoku earthquake, tsunami, and Fukushima nuclear accident: the Risk Policy Aftermath 3 #12;Personal experience in March 2011 Tsukuba 170km Tokyo 230km Fukushima Daiichi nuclear power

  12. Type B Accident Investigation Board Report Grout Injection Operator...

    Energy Savers [EERE]

    and no damage to any structures inside the calvareum (i.e., no evidence of brain injury). Page 16 2.4. Investigation Readiness and Accident Scene Preservation The...

  13. Some methods of estimating uncertainty in accident reconstruction

    E-Print Network [OSTI]

    Milan Batista

    2011-07-20

    In the paper four methods for estimating uncertainty in accident reconstruction are discussed: total differential method, extreme values method, Gauss statistical method, and Monte Carlo simulation method. The methods are described and the program solutions are given.

  14. Modeling control room crews for accident sequence analysis

    E-Print Network [OSTI]

    Huang, Y. (Yuhao)

    1991-01-01

    This report describes a systems-based operating crew model designed to simulate the behavior of an nuclear power plant control room crew during an accident scenario. This model can lead to an improved treatment of potential ...

  15. Type B Accident Investigation Board Report BNFL, Inc. Employee...

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

    17, 2003, at approximately 7:15 a.m., an accident occurred at the U.S. Department of Energy (DOE) East Tennessee Technology Park, Building K-31. An employee (Pipefitter) of...

  16. Spent-fuel-storage alternatives

    SciTech Connect (OSTI)

    Not Available

    1980-01-01

    The Spent Fuel Storage Alternatives meeting was a technical forum in which 37 experts from 12 states discussed storage alternatives that are available or are under development. The subject matter was divided into the following five areas: techniques for increasing fuel storage density; dry storage of spent fuel; fuel characterization and conditioning; fuel storage operating experience; and storage and transport economics. Nineteen of the 21 papers which were presented at this meeting are included in this Proceedings. These have been abstracted and indexed. (ATT)

  17. Neptunium storage at Hanford

    SciTech Connect (OSTI)

    Alderman, C.J.; Shiraga, S.S.; Schwartz, R.A.; Smith, R.J.; Wootan, D.W.

    1993-06-01

    A decision must be made regarding whether the United State`s stockpile of neptunium should be discarded into the waste stream or kept for the production of Pu-238. Although the cost of long term storage is not inconsequential, to dispose of the material means the closing of our option to maintain control over our Pu-238 stockpile. Within the Fuels and Materials Examination Facility at Hanford there exists a remotely operated facility that can be converted for neptunium storage. This paper describes the facility and the anticipated handling requirements.

  18. Storage tracking refinery trends

    SciTech Connect (OSTI)

    Saunders, J.

    1996-05-01

    Regulatory and marketplace shakeups have made the refining and petrochemical industries highly competitive. The fight to survive has forced refinery consolidations, upgrades and companywide restructurings. Bulk liquid storage terminals are following suit. This should generate a flurry of engineering and construction by the latter part of 1997. A growing petrochemical industry translates into rising storage needs. Industry followers forecasted flat petrochemical growth in 1996 due to excessive expansion in 1994 and 1995. But expansion is expected to continue throughout this year on the strength of several products.

  19. Carbon Storage Program

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 OutreachProductswsicloudwsiclouddenDVA N C E D B LReports from thecarbon captureCarbon Storage AtlasStorage

  20. Storage Ring Parameters

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust,Field-effect Photovoltaics -7541C.3X-rays3 Prepared by:'!TransportStorage RingStorage Ring

  1. Storage | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative Fuels Data CenterFinancialInvestingRenewable EnergyStaff andState andStorage Storage

  2. Material selection for accident tolerant fuel cladding

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

    Pint, B. A.; Terrani, K. A.; Yamamoto, Y.; Snead, L. L.

    2015-09-14

    Alternative cladding materials are being investigated for accident tolerance, which can be defined as >100X improvement (compared to current Zr-based alloys) in oxidation resistance in steam environments at ?1200°C for short (?4 h) times. After reviewing a wide range of candidates, current steam oxidation testing is being conducted on Mo, MAX phases and FeCrAl alloys. Recently reported low mass losses for Mo in steam at 800°C could not be reproduced. Both FeCrAl and MAX phase Ti2AlC form a protective alumina scale in steam. Therefore, commercial Ti2AlC that is not single phase, formed a much thicker oxide at 1200°C in steammore »and significant TiO2, and therefore may be challenging to use as a cladding or a coating. Alloy development for FeCrAl is seeking to maintain its steam oxidation resistance to 1475°C, while reducing its Cr content to minimize susceptibility to irradiation assisted Cr-rich ?’ formation. The composition effects and critical limits to retaining protective scale formation at >1400°C are still being evaluated.« less

  3. AQUIFER THERMAL ENERGY STORAGE-A SURVEY

    E-Print Network [OSTI]

    Tsang, Chin Fu

    2012-01-01

    1978, High temperature underground thermal energy storage,in Proceedings, Thermal Energy Storage in Aquifers Workshop:High temperature underground thermal energy storage, in ATES

  4. Distributed Generation with Heat Recovery and Storage

    E-Print Network [OSTI]

    Siddiqui, Afzal S.; Marnay, Chris; Firestone, Ryan M.; Zhou, Nan

    2008-01-01

    tiles for thermal energy storage,” working paper, Colorado1991). Wallboard with latent heat storage for passive solarR. (2000). Thermal energy storage for space cooling, Pacific

  5. Carbon Nanotube Films for Energy Storage Applications

    E-Print Network [OSTI]

    Kozinda, Alina

    2014-01-01

    Silicon Nanotubes and their Application to Energy Storage,&as an energy storage application of the amorphous-siliconof silicon nanowires hinders the energy storage capability [

  6. THERMAL ENERGY STORAGE IN AQUIFERS WORKSHOP

    E-Print Network [OSTI]

    Authors, Various

    2011-01-01

    Survey of Thermal Energy Storage in Aquifers Coupled withGeneration and Energy Storage," presented at Frontiers ofStudy of Underground Energy Storage Using High-Pressure,

  7. Carbon-based Materials for Energy Storage

    E-Print Network [OSTI]

    Rice, Lynn Margaret

    2012-01-01

    based Materials for Energy Storage A dissertation submittedbased Materials for Energy storage by Lynn Margaret Ricewind are intermittent. Energy storage systems, then, that

  8. Water Heaters (Storage Oil) | Department of Energy

    Energy Savers [EERE]

    Oil) Water Heaters (Storage Oil) Water Heater, Storage Oil - v1.0.xlsx More Documents & Publications Water Heaters (Tankless Electric) Water Heaters (Storage Electric)...

  9. Electric Storage in California's Commercial Buildings

    E-Print Network [OSTI]

    Stadler, Michael

    2014-01-01

    Effect of Heat and Electricity Storage and Reliability onNM, USA. [37] Electricity Storage Association, Morgan Hill,dimensionless d. electricity storage loss factor for the EV

  10. Storage Viability and Optimization Web Service

    E-Print Network [OSTI]

    Stadler, Michael

    2010-01-01

    Effect of Heat and Electricity Storage and Reliability onthe final report for the Electricity Storage Viability andof utility electricity purchase, on-site generation, storage

  11. Hydrogen Storage Research and Development Activities | Department...

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

    Hydrogen Storage Research and Development Activities Hydrogen Storage Research and Development Activities DOE's hydrogen storage research and development (R&D) activities are aimed...

  12. MASS STORAGE SYSTEMS AND LARGE RESEARCH LIBRARIES

    E-Print Network [OSTI]

    Baker, James A.

    2013-01-01

    Symposium on Mass Storage Systems, Denver, CO, April15-17, 1980 MASS STORAGE SYSTEMS AND LARGE RESEARCHSymposium on Mass Storage Systems, Denver, Colorado, April

  13. THERMAL ENERGY STORAGE IN AQUIFERS WORKSHOP

    E-Print Network [OSTI]

    Authors, Various

    2011-01-01

    D. Todd, (1973). Heat storage Systems in the L - Temperaturements for Energy Storage Systems, Los Alamos Scientificdirector for Physi- cal Storage Systems. Under Jim are three

  14. AQUIFER THERMAL ENERGY STORAGE-A SURVEY

    E-Print Network [OSTI]

    Tsang, Chin Fu

    2012-01-01

    the prob- lem of seasonal storage of thermal energy (Matheyto study seasonal storage of thermal energy: winter storagewithin the Seasonal Thermal Energy Storage Program managed

  15. Nanostructured Materials for Energy Generation and Storage

    E-Print Network [OSTI]

    Khan, Javed Miller

    2012-01-01

    for Electrochemical Energy Storage Nanostructured Electrodesof the batteries and their energy storage efficiency. viifor Nanostructure-Based Energy Storage and Generation Tech-

  16. AQUIFER THERMAL ENERGY STORAGE-A SURVEY

    E-Print Network [OSTI]

    Tsang, Chin Fu

    2012-01-01

    High temperature underground thermal energy storage, inProceedings, Thermal Energy Storage in Aquifers Workshop:underground thermal energy storage, in ATES newsletter:

  17. THERMAL ENERGY STORAGE IN AQUIFERS WORKSHOP

    E-Print Network [OSTI]

    Authors, Various

    2011-01-01

    Survey of Thermal Energy Storage in Aquifers Coupled withLow Temperature Thermal Energy Storage Program of Oak Ridgefor Seasonal Thermal Energy Storage: An Overview of the DOE-

  18. Pest Management For Grain Storage and Fumigation

    E-Print Network [OSTI]

    Dyer, Bill

    Pest Management For Grain Storage and Fumigation Seed Treatment -Pest Control- Grain Storage & Seed MANAGEMENT FOR GRAIN STORAGE AND FUMIGATION Introduction .................................................................................................................................................................. 12 Resistance Management Issues

  19. EIA - Natural Gas Storage Data & Analysis

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    Storage Weekly Working Gas in Underground Storage U.S. Natural gas inventories held in underground storage facilities by East, West, and Producing regions (weekly). Underground...

  20. Distributed Generation with Heat Recovery and Storage

    E-Print Network [OSTI]

    Siddiqui, Afzal S.; Marnay, Chris; Firestone, Ryan M.; Zhou, Nan

    2008-01-01

    Distributed Generation with Heat Recovery and Storage AfzalGeneration with Heat Recovery and Storage Manuscript Numberhere in order to focus on heat recovery and storage) utility

  1. Study on drywell cooler applicability to severe accident management

    SciTech Connect (OSTI)

    Nakagawa, Takahiro [Information and manufacturing systems division, Toshiba Plant Systems and Services Corporation, 8, Shinsugita-cho, Isogo-ku, Yokohama, 235-8523 (Japan); Akinaga, Makoto [Power and Industrial Systems R and D Center, Toshiba Corporation, 4-1 Ukishima-cho, Kawasaki-ku, Kawasaki, 210-0862 (Japan); Hamazaki, Ryoichi [Isogo Nuclear Engineering Center, Toshiba Corporation, 8, Shinsugita-cho, Isogo-ku, Yokohama, 235-8523 (Japan); Matsuo, Toshihiro [Nuclear Power Engineering Department, Tokyo Electric Power Company, 1-3 Uchisaiwai-cho 1-chome, Chiyoda-ku, Tokyo 100-0011 (Japan); Hashimoto, Kouji [Nuclear Plant Engineering Department, HITACHI, Ltd., 1-1, Saiwai-cho, 3-chome, Hitachi-shi, Ibaraki-ken, 317-8511 (Japan)

    2004-07-01

    This paper concerns applicability of drywell cooler (DWC) heat removal under severe accident condition in BWR plants. Newly developed heat removal models based on DWC heat removal experiments were built into the MAAP3 code. And then, two types of Japanese BWR were selected to evaluate DWC heat removal performance under typical severe accident scenarios. According to the results of the evaluation, DWC delays or prevents containment failure or venting. (authors)

  2. Extension of emergency operating procedures for severe accident management

    SciTech Connect (OSTI)

    Chiang, S.C. (Taiwan Power Company, Taipei (Taiwan, Province of China))

    1992-01-01

    To enhance the capability of reactor operators to cope with the hypothetical severe accident its the key issue for utilities. Taiwan Power Company has started the enhancement programs on extension of emergency operating procedures (EOPs). It includes the review of existing LOPs based on the conclusions and recommendations of probabilistic risk assessment studies to confirm the operator actions. Then the plant specific analysis for accident management strategy will be performed and the existing EOPs will be updated accordingly.

  3. Severe accident progression perspectives based on IPE results

    SciTech Connect (OSTI)

    Lehner, J.R.; Lin, C.C.; Pratt, W.T.; Drouin, M.

    1996-08-01

    Accident progression perspectives were gathered from the level 2 PRA analyses (the analysis of the accident after core damage has occurred involving the containment performance and the radionuclide release from the containment) described in the IPE submittals. Insights related to the containment failure modes, the releases associated with those failure modes, and the factors responsible for the types of containment failures and release sizes reported were obtained. Complete results are discussed in NUREG-1560 and summarized here.

  4. PRODUCING CONTINUOUSLY GROWING DUCK AND AVIAN CELL LINES FROM PRIMAY AVIAN CELLS 

    E-Print Network [OSTI]

    Franklin, Zachary 1986-

    2012-05-02

    Primary cells from cockatiel and duck embryos were prepared from unhatched cockatiel and duck eggs. They were expanded and frozen for storage and further use and evaluation. To transform the primary cells and generate a continuous cell line...

  5. NV Energy Electricity Storage Valuation

    SciTech Connect (OSTI)

    Ellison, James F.; Bhatnagar, Dhruv; Samaan, Nader A.; Jin, Chunlian

    2013-06-30

    This study examines how grid-level electricity storage may benet the operations of NV Energy in 2020, and assesses whether those benets justify the cost of the storage system. In order to determine how grid-level storage might impact NV Energy, an hourly production cost model of the Nevada Balancing Authority (\\BA") as projected for 2020 was built and used for the study. Storage facilities were found to add value primarily by providing reserve. Value provided by the provision of time-of-day shifting was found to be limited. If regulating reserve from storage is valued the same as that from slower ramp rate resources, then it appears that a reciprocating engine generator could provide additional capacity at a lower cost than a pumped storage hydro plant or large storage capacity battery system. In addition, a 25-MW battery storage facility would need to cost $650/kW or less in order to produce a positive Net Present Value (NPV). However, if regulating reserve provided by storage is considered to be more useful to the grid than that from slower ramp rate resources, then a grid-level storage facility may have a positive NPV even at today's storage system capital costs. The value of having storage provide services beyond reserve and time-of-day shifting was not assessed in this study, and was therefore not included in storage cost-benefit calculations.

  6. THERMAL ANALYSIS OF A 9975 PACKAGE IN A FACILITY FIRE ACCIDENT

    SciTech Connect (OSTI)

    Gupta, N.

    2011-02-14

    Surplus plutonium bearing materials in the U.S. Department of Energy (DOE) complex are stored in the 3013 containers that are designed to meet the requirements of the DOE standard DOE-STD-3013. The 3013 containers are in turn packaged inside 9975 packages that are designed to meet the NRC 10 CFR Part 71 regulatory requirements for transporting the Type B fissile materials across the DOE complex. The design requirements for the hypothetical accident conditions (HAC) involving a fire are given in 10 CFR 71.73. The 9975 packages are stored at the DOE Savannah River Site in the K-Area Material Storage (KAMS) facility for long term of up to 50 years. The design requirements for safe storage in KAMS facility containing multiple sources of combustible materials are far more challenging than the HAC requirements in 10 CFR 71.73. While the 10 CFR 71.73 postulates an HAC fire of 1475 F and 30 minutes duration, the facility fire calls for a fire of 1500 F and 86 duration. This paper describes a methodology and the analysis results that meet the design limits of the 9975 component and demonstrate the robustness of the 9975 package.

  7. Type B Accident Investigation Board Report on the March 27, 1998, Rotating Shaft Accident at the Ames Laboratory, Ames, Iowa

    Broader source: Energy.gov [DOE]

    This report is an independent product of the Type B Accident Investigation Board appointed by John Kennedy, Acting Manager, Chicago Operations Office, U.S. Department of Energy (DOE).

  8. Storage and Infrastructure

    E-Print Network [OSTI]

    Madey, Gregory R.

    ;Cheaper to Collect RFIDs Sensor Nets The WWW, Screen Scraping, Google Searches Life in CyberSpace - Log Files, Digital Traces, MetaData Faster Computers ==> More Data to Study #12;Data Driven Discovery Organizations, Cyberinfrastructure #12;Research Opportunities & Challenges Sensors, Sensor Networks Storage

  9. Chit-based Remote Storage

    E-Print Network [OSTI]

    Paluska, Justin Mazzola

    We propose a model for reliable remote storage founded on contract law. Consumers submit their bits to storage providers in exchange for a chit. A chit is a cryptographically secure, verifiable contract between a consumer ...

  10. Hydrogen Storage Technical Team Roadmap

    SciTech Connect (OSTI)

    2013-06-01

    The mission of the Hydrogen Storage Technical Team is to accelerate research and innovation that will lead to commercially viable hydrogen-storage technologies that meet the U.S. DRIVE Partnership goals.

  11. Status of Hydrogen Storage Technologies

    Office of Energy Efficiency and Renewable Energy (EERE)

    The current status in terms of weight, volume, and cost of various hydrogen storage technologies is shown below. These values are estimates from storage system developers and the R&D community...

  12. Silo Storage Preconceptual Design

    SciTech Connect (OSTI)

    Stephanie L. Austad; Patrick W. Bragassa; Kevin M Croft; David S Ferguson; Scott C Gladson; Annette L Shafer; John H Weathersby

    2012-09-01

    The National Nuclear Security Administration (NNSA) has a need to develop and field a low-cost option for the long-term storage of a variety of radiological material. The storage option’s primary requirement is to provide both environmental and physical protection of the materials. Design criteria for this effort require a low initial cost and minimum maintenance over a 50-year design life. In 1999, Argonne National Laboratory-West was tasked with developing a dry silo storage option for the BN-350 Spent Fuel in Aktau Kazakhstan. Argon’s design consisted of a carbon steel cylinder approximately 16 ft long, 18 in. outside diameter and 0.375 in. wall thickness. The carbon steel silo was protected from corrosion by a duplex coating system consisting of zinc and epoxy. Although the study indicated that the duplex coating design would provide a design life well in excess of the required 50 years, the review board was concerned because of the novelty of the design and the lack of historical use. In 2012, NNSA tasked Idaho National Laboratory (INL) with reinvestigating the silo storage concept and development of alternative corrosion protection strategies. The 2012 study, “Silo Storage Concepts, Cathodic Protection Options Study” (INL/EST-12-26627), concludes that the option which best fits the design criterion is a passive cathotic protection scheme, consisting of a carbon steel tube coated with zinc or a zinc-aluminum alloy encapsulated in either concrete or a cement grout. The hot dipped zinc coating option was considered most efficient, but the flame-sprayed option could be used if a thicker zinc coating was determined to be necessary.

  13. Webinar: Hydrogen Storage Materials Requirements

    Broader source: Energy.gov [DOE]

    Video recording and text version of the webinar titled, Hydrogen Storage Materials Requirements, originally presented on June 25, 2013.

  14. Racing line optimization

    E-Print Network [OSTI]

    Xiong, Ying, S.M. Massachusetts Institute of Technology

    2010-01-01

    Although most racers are good at controlling their cars, world champions are always talented at choosing the right racing line while others mostly fail to do that. Optimal racing line selection is a critical problem in car ...

  15. The Power of Energy Storage

    E-Print Network [OSTI]

    Sadoulet, Elisabeth

    The Power of Energy Storage How to Increase Deployment in California to Reduce Greenhouse Gas;1Berkeley Law \\ UCLA Law The Power of Energy Storage: How to Increase Deployment in California to Reduce Greenhouse Gas Emissions Executive Summary: Expanding Energy Storage in California Sunshine and wind, even

  16. HIERARCHICAL STORAGE SYSTEMS FOR INTERACTIVE

    E-Print Network [OSTI]

    Chan, Shueng-Han Gary

    HIERARCHICAL STORAGE SYSTEMS FOR INTERACTIVE VIDEO­ON­DEMAND Shueng­Han Gary Chan and Fouad A; Hierarchical Storage Systems for Interactive Video­On­Demand Shueng­Han Gary Chan and Fouad A. Tobagi Technical­9040 pubs@shasta.stanford.edu Abstract On­demand video servers based on hierarchical storage systems

  17. Electrical Energy Storage: Stan Whittingham

    E-Print Network [OSTI]

    Suzuki, Masatsugu

    1 p. 1 Electrical Energy Storage: Stan Whittingham Report of DOE workshop, April 2007 A Cleaner and Energy Independent America through Chemistry Chemical Storage: Batteries, today and tomorrow http needed in Energy Storage Lithium Economy not Hydrogen Economy #12;9 p. 9 Batteries are key to an economy

  18. Energy Storage: Current landscape for alternative energy

    E-Print Network [OSTI]

    Energy Storage: Current landscape for alternative energy storage technologies and what the future may hold for multi-scale storage applications Presented by: Dave Lucero, Director Alternative Energy · Industry initiatives · Technology · Energy Storage Market · EaglePicher initiatives · Summary #12

  19. Storage depot for radioactive material

    DOE Patents [OSTI]

    Szulinski, Milton J. (Richland, WA)

    1983-01-01

    Vertical drilling of cylindrical holes in the soil, and the lining of such holes, provides storage vaults called caissons. A guarded depot is provided with a plurality of such caissons covered by shielded closures preventing radiation from penetrating through any linear gap to the atmosphere. The heat generated by the radioactive material is dissipated through the vertical liner of the well into the adjacent soil and thus to the ground surface so that most of the heat from the radioactive material is dissipated into the atmosphere in a manner involving no significant amount of biologically harmful radiation. The passive cooling of the radioactive material without reliance upon pumps, personnel, or other factor which might fail, constitutes one of the most advantageous features of this system. Moreover this system is resistant to damage from tornadoes or earthquakes. Hermetically sealed containers of radioactive material may be positioned in the caissons. Loading vehicles can travel throughout the depot to permit great flexibility of loading and unloading radioactive materials. Radioactive material can be shifted to a more closely spaced caisson after ageing sufficiently to generate much less heat. The quantity of material stored in a caisson is restricted by the average capacity for heat dissipation of the soil adjacent such caisson.

  20. Feasibility of on-line fuel-condition monitoring. [PWR; BWR

    SciTech Connect (OSTI)

    Petti, D.A.; Osetek, D.J.; Croucher, D.W.; Hartwell, J.K.

    1982-01-01

    The relationship between fuel rod damage and fission product release is investigated to assess the feasibility of using on-line gamma spectroscopy of reactor coolant to estimate not only numbers of detected fuel rods, but also the type of core damage which may occur during an accident or off-normal transient. Fission product release signatures for various fuel conditions and accident scenarios are compared, and unique indicators of fuel damage, ranging from cladding pinholes to severely damaged fuel rods, are suggested, The configuration of monitoring hardware and data analysis soft ware are described, and the benefits, development needs, and usefulness of the envisaged power plant system are discussed.

  1. MELCOR Analysis of Steam Generator Tube Creep Rupture in Station Blackout Severe Accident

    SciTech Connect (OSTI)

    Liao, Y.; Vierow, K. [Purdue University (United States)

    2005-12-15

    A pressurized water reactor steam generator tube rupture (SGTR) is of concern because it represents a bypass of the containment for radioactive materials to the environment. In a station blackout accident, tube integrity could be threatened by creep rupture, particularly if cracks are present in the tube walls. Methods are developed herein to improve assessment capabilities for SGTR by using the severe-accident code MELCOR. Best-estimate assumptions based on recent research and computational fluid dynamics calculations are applied in the MELCOR analysis to simulate two-dimensional natural circulation and to determine the relative creep-rupture timing in the reactor coolant pressure boundary components. A new method is developed to estimate the steam generator (SG) hottest tube wall temperature and the tube critical crack size for the SG tubes to fail first. The critical crack size for SG tubes to fail first is estimated to be 20% of the wall thickness larger than by a previous analysis. Sensitivity studies show that the failure sequence would change if some assumptions are modified. In particular, the uncertainty in the countercurrent flow limit model could reverse the failure sequence of the SG tubes and surge line.

  2. Human factors review for Severe Accident Sequence Analysis (SASA)

    SciTech Connect (OSTI)

    Krois, P.A.; Haas, P.M.; Manning, J.J.; Bovell, C.R.

    1984-01-01

    The paper will discuss work being conducted during this human factors review including: (1) support of the Severe Accident Sequence Analysis (SASA) Program based on an assessment of operator actions, and (2) development of a descriptive model of operator severe accident management. Research by SASA analysts on the Browns Ferry Unit One (BF1) anticipated transient without scram (ATWS) was supported through a concurrent assessment of operator performance to demonstrate contributions to SASA analyses from human factors data and methods. A descriptive model was developed called the Function Oriented Accident Management (FOAM) model, which serves as a structure for bridging human factors, operations, and engineering expertise and which is useful for identifying needs/deficiencies in the area of accident management. The assessment of human factors issues related to ATWS required extensive coordination with SASA analysts. The analysis was consolidated primarily to six operator actions identified in the Emergency Procedure Guidelines (EPGs) as being the most critical to the accident sequence. These actions were assessed through simulator exercises, qualitative reviews, and quantitative human reliability analyses. The FOAM descriptive model assumes as a starting point that multiple operator/system failures exceed the scope of procedures and necessitates a knowledge-based emergency response by the operators. The FOAM model provides a functionally-oriented structure for assembling human factors, operations, and engineering data and expertise into operator guidance for unconventional emergency responses to mitigate severe accident progression and avoid/minimize core degradation. Operators must also respond to potential radiological release beyond plant protective barriers. Research needs in accident management and potential uses of the FOAM model are described. 11 references, 1 figure.

  3. Project Profile: Carbon Dioxide Shuttling Thermochemical Storage...

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

    Project Profile: Carbon Dioxide Shuttling Thermochemical Storage Using Strontium Carbonate Project Profile: Carbon Dioxide Shuttling Thermochemical Storage Using Strontium...

  4. Fact Sheet: Energy Storage Technology Advancement Partnership...

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

    Technology Advancement Partnership (October 2012) Fact Sheet: Energy Storage Technology Advancement Partnership (October 2012) The Energy Storage Technology Advancement Partnership...

  5. Combinatorial Approaches for Hydrogen Storage Materials (presentation...

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

    Approaches for Hydrogen Storage Materials (presentation) Combinatorial Approaches for Hydrogen Storage Materials (presentation) Presentation on NIST Combinatorial Methods at the...

  6. Nanoscale data storage

    E-Print Network [OSTI]

    J. C. Li

    2007-01-29

    The object of this article is to review the development of ultrahigh-density, nanoscale data storage, i.e., nanostorage. As a fundamentally new type of storage system, the recording mechanisms of nanostorage may be completely different to those of the traditional devices. Currently, two types of molecules are being studied for potential application in nanostorage. One is molecular electronic elements including molecular wires, rectifiers, switches, and transistors. The other approach employs nanostructured materials such as nanotubes, nanowires, and nanoparticles. The challenges for nanostorage are not only the materials, ultrahigh data-densities, fabrication-costs, device operating temperatures and large-scale integration, but also the development of the physical principles and models. There are already some breakthroughs obtained, but it is still unclear what kind of nanostorage systems can ultimately replace the current silicon based transistors. A promising candidate may be a molecular-nanostructure hybrid device with sub-5 nm dimensions.

  7. Superconducting magnetic energy storage

    SciTech Connect (OSTI)

    Hassenzahl, W.

    1988-08-01

    Recent programmatic developments in Superconducting Magnetic Energy Storage (SMES) have prompted renewed and widespread interest in this field. In mid 1987 the Defense Nuclear Agency, acting for the Strategic Defense Initiative Office, issued a request for proposals for the design and construction of SMES Engineering Test Model (ETM). Two teams, one led by Bechtel and the other by Ebasco, are now engaged in the first phase of the development of a 10 to 20 MWhr ETM. This report presents the rationale for energy storage on utility systems, describes the general technology of SMES, and explains the chronological development of the technology. The present ETM program is outlined; details of the two projects for ETM development are described in other papers in these proceedings. The impact of high T/sub c/ materials on SMES is discussed. 69 refs., 3 figs., 3 tabs.

  8. OSSA - An optimized approach to severe accident management: EPR application

    SciTech Connect (OSTI)

    Sauvage, E. C.; Prior, R.; Coffey, K. [AREVA, FRAMATOME-ANP SAS, Paris, 92084 La Defense (France); Mazurkiewicz, S. M. [AREVA, FRAMATOME-ANP Inc, Lynchburg, VA 24506-0935 (United States)

    2006-07-01

    There is a recognized need to provide nuclear power plant technical staff with structured guidance for response to a potential severe accident condition involving core damage and potential release of fission products to the environment. Over the past ten years, many plants worldwide have implemented such guidance for their emergency technical support center teams either by following one of the generic approaches, or by developing fully independent approaches. There are many lessons to be learned from the experience of the past decade, in developing, implementing, and validating severe accident management guidance. Also, though numerous basic approaches exist which share common principles, there are differences in the methodology and application of the guidelines. AREVA/Framatome-ANP is developing an optimized approach to severe accident management guidance in a project called OSSA ('Operating Strategies for Severe Accidents'). There are still numerous operating power plants which have yet to implement severe accident management programs. For these, the option to use an updated approach which makes full use of lessons learned and experience, is seen as a major advantage. Very few of the current approaches covers all operating plant states, including shutdown states with the primary system closed and open. Although it is not necessary to develop an entirely new approach in order to add this capability, the opportunity has been taken to develop revised full scope guidance covering all plant states in addition to the fuel in the fuel building. The EPR includes at the design phase systems and measures to minimize the risk of severe accident and to mitigate such potential scenarios. This presents a difference in comparison with existing plant, for which severe accidents where not considered in the design. Thought developed for all type of plants, OSSA will also be applied on the EPR, with adaptations designed to take into account its favourable situation in that field. This revised approach will incorporate a number of new features which will simplify and streamline the guidance material while ensuring comprehensive guidance for response to any severe accident. Examples of such features include : - Identification of severe accident challenges based on plant specific studies. - Revision of the split of responsibilities between operations and technical support center staff. - Fixed setpoint entry conditions, ensuring that the transition from emergency procedures takes place at a consistent core/fuel condition (regardless of scenario), and which fixes the time window available to attempt ultimate preventive measures. - A safety function concept for monitoring plant conditions (in the control room). - An integrated graphic-based diagnostic tool including entry condition, challenge prioritization, and exit condition monitoring to be used by the technical support team. This paper describes the basic features of OSSA, and project status. (authors)

  9. Severe Accident Sequence Analysis Program: Anticipated transient without scram simulations for Browns Ferry Nuclear Plant Unit 1

    SciTech Connect (OSTI)

    Dallman, R J; Gottula, R C; Holcomb, E E; Jouse, W C; Wagoner, S R; Wheatley, P D

    1987-05-01

    An analysis of five anticipated transients without scram (ATWS) was conducted at the Idaho National Engineering Laboratory (INEL). The five detailed deterministic simulations of postulated ATWS sequences were initiated from a main steamline isolation valve (MSIV) closure. The subject of the analysis was the Browns Ferry Nuclear Plant Unit 1, a boiling water reactor (BWR) of the BWR/4 product line with a Mark I containment. The simulations yielded insights to the possible consequences resulting from a MSIV closure ATWS. An evaluation of the effects of plant safety systems and operator actions on accident progression and mitigation is presented.

  10. Radiological Impact Assessment (RIA) following a postulated accident in PHWRS

    SciTech Connect (OSTI)

    Soni, N.; Kansal, M.; Rammohan, H. P.; Malhotra, P. K.

    2012-07-01

    Radiological Impact Assessment (RIA) following postulated accident i.e Loss of Coolant Accident (LOCA) with failed Emergency Core Cooling System (ECCS), performed as part of the reactor safety analysis of a typical 700 MWe Indian Pressurized Heavy Water Reactor(PHWR). The rationale behind the assessment is that the public needs to be protected in the event that the postulated accident results in radionuclide release outside containment. Radionuclides deliver dose to the human body through various pathways namely, plume submersion, exposure due to ground deposition, inhalation and ingestion. The total exposure dose measured in terms of total effective dose equivalent (TEDE) is the sum of doses to a hypothetical adult human at exclusion zone boundary by all the exposure pathways. The analysis provides the important inputs to decide upon the type of emergency counter measures to be adopted during the postulated accident. The importance of the various pathways in terms of contribution to the total effective dose equivalent(TEDE) is also assessed with respect to time of exposure. Inhalation and plume gamma dose are the major contributors towards TEDE during initial period of accident whereas ingestion and ground shine dose start dominating in TEDE in the extended period of exposure. Moreover, TEDE is initially dominated by I-131, Kr-88, Te-132, I-133 and Sr-89, whereas, as time progresses, Xe-133,I-131 and Te-132 become the main contributors. (authors)

  11. Accident Sequence Evaluation Program: Human reliability analysis procedure

    SciTech Connect (OSTI)

    Swain, A.D.

    1987-02-01

    This document presents a shortened version of the procedure, models, and data for human reliability analysis (HRA) which are presented in the Handbook of Human Reliability Analysis With emphasis on Nuclear Power Plant Applications (NUREG/CR-1278, August 1983). This shortened version was prepared and tried out as part of the Accident Sequence Evaluation Program (ASEP) funded by the US Nuclear Regulatory Commission and managed by Sandia National Laboratories. The intent of this new HRA procedure, called the ''ASEP HRA Procedure,'' is to enable systems analysts, with minimal support from experts in human reliability analysis, to make estimates of human error probabilities and other human performance characteristics which are sufficiently accurate for many probabilistic risk assessments. The ASEP HRA Procedure consists of a Pre-Accident Screening HRA, a Pre-Accident Nominal HRA, a Post-Accident Screening HRA, and a Post-Accident Nominal HRA. The procedure in this document includes changes made after tryout and evaluation of the procedure in four nuclear power plants by four different systems analysts and related personnel, including human reliability specialists. The changes consist of some additional explanatory material (including examples), and more detailed definitions of some of the terms. 42 refs.

  12. Maui energy storage study.

    SciTech Connect (OSTI)

    Ellison, James; Bhatnagar, Dhruv; Karlson, Benjamin

    2012-12-01

    This report investigates strategies to mitigate anticipated wind energy curtailment on Maui, with a focus on grid-level energy storage technology. The study team developed an hourly production cost model of the Maui Electric Company (MECO) system, with an expected 72 MW of wind generation and 15 MW of distributed photovoltaic (PV) generation in 2015, and used this model to investigate strategies that mitigate wind energy curtailment. It was found that storage projects can reduce both wind curtailment and the annual cost of producing power, and can do so in a cost-effective manner. Most of the savings achieved in these scenarios are not from replacing constant-cost diesel-fired generation with wind generation. Instead, the savings are achieved by the more efficient operation of the conventional units of the system. Using additional storage for spinning reserve enables the system to decrease the amount of spinning reserve provided by single-cycle units. This decreases the amount of generation from these units, which are often operated at their least efficient point (at minimum load). At the same time, the amount of spinning reserve from the efficient combined-cycle units also decreases, allowing these units to operate at higher, more efficient levels.

  13. DESIGN OF VISIBLE DIAGNOSTIC BEAMLINE FOR NSLS2 STORAGE RING

    SciTech Connect (OSTI)

    Cheng, W.; Fernandes, H.; Hseuh, H.; Kosciuk, B.; Krinsky, S.; Singh, O.

    2011-03-28

    A visible synchrotron light monitor (SLM) beam line has been designed at the NSLS2 storage ring, using the bending magnet radiation. A retractable thin absorber will be placed in front of the first mirror to block the central x-rays. The first mirror will reflect the visible light through a vacuum window. The light is guided by three 6-inch diameter mirrors into the experiment hutch. In this paper, we will describe design work on various optical components in the beamline. The ultra high brightness NSLS-II storage ring is under construction at Brookhaven National Laboratory. It will have 3GeV, 500mA electron beam circulating in the 792m ring, with very low emittance (0.9nm.rad horizontal and 8pm.rad vertical). The ring is composed of 30 DBA cells with 15 fold symmetry. Three damping wigglers will be installed in long straight sections 8, 18 and 28 to lower the emittance. While electrons pass through the bending magnet, synchrotron radiation will be generated covering a wide spectrum. There are other insertion devices in the storage ring which will generate shorter wavelength radiation as well. Synchrotron radiation has been widely used as diagnostic tool to measure the transverse and longitudinal profile. Three synchrotron light beam lines dedicated for diagnostics are under design and construction for the NSLS-II storage ring: two x-ray beam lines (pinhole and CRL) with the source points from Cell 22 BM{_}A (first bending in the DBA cell) and Cell22 three-pole wiggler; the third beam line is using visible part of radiation from Cell 30 BM{_}B (second bending magnet from the cell). Our paper focuses on the design of the visible beam line - SLM.

  14. Phase 1A Final Report for the AREVA Team Enhanced Accident Tolerant Fuels Concepts

    SciTech Connect (OSTI)

    Morrell, Mike E.

    2015-03-19

    In response to the Department of Energy (DOE) funded initiative to develop and deploy lead fuel assemblies (LFAs) of Enhanced Accident Tolerant Fuel (EATF) into a US reactor within 10 years, AREVA put together a team to develop promising technologies for improved fuel performance during off normal operations. This team consisted of the University of Florida (UF) and the University of Wisconsin (UW), Savannah River National Laboratory (SRNL), Duke Energy and Tennessee Valley Authority (TVA). This team brought broad experience and expertise to bear on EATF development. AREVA has been designing; manufacturing and testing nuclear fuel for over 50 years and is one of the 3 large international companies supplying fuel to the nuclear industry. The university and National Laboratory team members brought expertise in nuclear fuel concepts and materials development. Duke and TVA brought practical utility operating experience. This report documents the results from the initial “discovery phase” where the team explored options for EATF concepts that provide enhanced accident tolerance for both Design Basis (DB) and Beyond Design Basis Events (BDB). The main driver for the concepts under development were that they could be implemented in a 10 year time frame and be economically viable and acceptable to the nuclear fuel marketplace. The economics of fuel design make this DOE funded project very important to the nuclear industry. Even incremental changes to an existing fuel design can cost in the range of $100M to implement through to LFAs. If this money is invested evenly over 10 years then it can take the fuel vendor several decades after the start of the project to recover their initial investment and reach a breakeven point on the initial investment. Step or radical changes to a fuel assembly design can cost upwards of $500M and will take even longer for the fuel vendor to recover their investment. With the projected lifetimes of the current generation of nuclear power plants large scale investment by the fuel vendors is difficult to justify. Specific EATF enhancements considered by the AREVA team were; Improved performance in DB and BDB conditions; Reduced release to the environment in a catastrophic accident; Improved performance during normal operating conditions; Improved performance if US reactors start to load follow; Equal or improved economics of the fuel; and Improvements to the fuel behavior to support future transportation and storage of the used nuclear fuel (UNF). In pursuit of the above enhancements, EATF technology concepts that our team considered were; Additives to the fuel pellets which included; Chromia doping to increase fission gas retention. Chromia doping has the potential to improve load following characteristics, improve performance of the fuel pellet during clad failure, and potentially lock up cesium into the fuel matrix; Silicon Carbide (SiC) Fibers to improve thermal heat transfer in normal operating conditions which also improves margin in accident conditions and the potential to lock up iodine into the fuel matrix; Nano-diamond particles to enhance thermal conductivity; Coatings on the fuel cladding; and Nine coatings on the existing Zircaloy cladding to increase coping time and reduce clad oxidation and hydrogen generation during accident conditions, as well as reduce hydrogen pickup and mitigate hydride reorientation in the cladding. To facilitate the development process AREVA adopted a formal “Gate Review Process” (GR) that was used to review results and focus resources onto promising technologies to reduce costs and identify the technologies that would potentially be carried forward to LFAs within a 10 year period. During the initial discovery phase of the project AREVA took the decision to be relatively hands off and allow our university and National Laboratory partners to be free thinking and consider options that would not be constrained by preconceived ideas from the fuel vendor. To counter this and to keep the partners focused, the GR process was utilized. During this GR process each

  15. ATWS at Browns Ferry Unit One - accident sequence analysis

    SciTech Connect (OSTI)

    Harrington, R.M.; Hodge, S.A.

    1984-07-01

    This study describes the predicted response of Unit One at the Browns Ferry Nuclear Plant to a postulated complete failure to scram following a transient occurrence that has caused closure of all Main Steam Isolation Valves (MSIVs). This hypothetical event constitutes the most severe example of the type of accident classified as Anticipated Transient Without Scram (ATWS). Without the automatic control rod insertion provided by scram, the void coefficient of reactivity and the mechanisms by which voids are formed in the moderator/coolant play a dominant role in the progression of the accident. Actions taken by the operator greatly influence the quantity of voids in the coolant and the effect is analyzed in this report. The progression of the accident sequence under existing and under recommended procedures is discussed. For the extremely unlikely cases in which equipment failure and wrongful operator actions might lead to severe core damage, the sequence of emergency action levels and the associated timing of events are presented.

  16. Effect of shape reactivity on the rod-ejection accident

    SciTech Connect (OSTI)

    Neogy, P.; Carew, J.F.

    1982-09-01

    The shape reactivity has a significant influence on the rod ejection accident. After the control rod is fully ejected from the core, the neutron flux undergoes a large reduction at the ejected rod location. The corresponding effect on the control reactivity is comparable in magnitude to the Doppler reactivity, and makes a significant contribution to limiting the power excursion during the transient. The neglect of this effect in point kinetics and space time synthesis analyses of the rod ejection accident may account in part for the large degree of conservatism usually associated with these analyses.

  17. Series Transmission Line Transformer

    DOE Patents [OSTI]

    Buckles, Robert A. (Livermore, CA); Booth, Rex (Livermore, CA); Yen, Boris T. (El Cerrito, CA)

    2004-06-29

    A series transmission line transformer is set forth which includes two or more of impedance matched sets of at least two transmissions lines such as shielded cables, connected in parallel at one end ans series at the other in a cascading fashion. The cables are wound about a magnetic core. The series transmission line transformer (STLT) which can provide for higher impedance ratios and bandwidths, which is scalable, and which is of simpler design and construction.

  18. Neutrino signals in electron-capture storage-ring experiments

    E-Print Network [OSTI]

    Avraham Gal

    2015-05-26

    Neutrino signals in electron-capture storage-ring experiments at GSI are reconsidered, with special emphasis placed on the quasi-circular motion of the daughter ions in two-body decays. Whereas parent-ion decay rates cannot exhibit modulation with the several-second period reported in these experiments, the time evolution of the detected daughter ions is shown to produce oscillations that under certain conditions may provide resolution of the `GSI Oscillations' puzzle. New dedicated storage-ring or trap experiments could look up for these oscillations.

  19. Safe Home Food Storage 

    E-Print Network [OSTI]

    Van Laanen, Peggy

    2002-08-22

    leftovers? The charts in this publication give storage times for many leftover foods. Planning and us- ing leftovers carefully can save money and time. To prevent food-borne illness, it is important to prepare and handle foods properly: a78 Wash your hands.... Cooked fish or shellfish 2-3 days 3 months Canned fish or shellfish (unopened) 12 months (opened) 1 day Surimi seafood 2 weeks 9 months Fruits Fresh Do not wash fruit before storing?mois- Apples 1 month ture encourages spoilage?but wash Apricots, avocados...

  20. Entanglement Storage Units

    E-Print Network [OSTI]

    T. Caneva; T. Calarco; S. Montangero

    2012-09-27

    We introduce a protocol based on optimal control to drive many body quantum systems into long-lived entangled states, protected from decoherence by big energy gaps, without requiring any apriori knowledge of the system. With this approach it is possible to implement scalable entanglement-storage units. We test the protocol in the Lipkin-Meshkov-Glick model, a prototype many-body quantum system that describes different experimental setups, and in the ordered Ising chain, a model representing a possible implementation of a quantum bus.

  1. Gas Storage Technology Consortium

    SciTech Connect (OSTI)

    Joel Morrison; Elizabeth Wood; Barbara Robuck

    2010-09-30

    The EMS Energy Institute at The Pennsylvania State University (Penn State) has managed the Gas Storage Technology Consortium (GSTC) since its inception in 2003. The GSTC infrastructure provided a means to accomplish industry-driven research and development designed to enhance the operational flexibility and deliverability of the nation's gas storage system, and provide a cost-effective, safe, and reliable supply of natural gas to meet domestic demand. The GSTC received base funding from the U.S. Department of Energy's (DOE) National Energy Technology Laboratory (NETL) Oil & Natural Gas Supply Program. The GSTC base funds were highly leveraged with industry funding for individual projects. Since its inception, the GSTC has engaged 67 members. The GSTC membership base was diverse, coming from 19 states, the District of Columbia, and Canada. The membership was comprised of natural gas storage field operators, service companies, industry consultants, industry trade organizations, and academia. The GSTC organized and hosted a total of 18 meetings since 2003. Of these, 8 meetings were held to review, discuss, and select proposals submitted for funding consideration. The GSTC reviewed a total of 75 proposals and committed co-funding to support 31 industry-driven projects. The GSTC committed co-funding to 41.3% of the proposals that it received and reviewed. The 31 projects had a total project value of $6,203,071 of which the GSTC committed $3,205,978 in co-funding. The committed GSTC project funding represented an average program cost share of 51.7%. Project applicants provided an average program cost share of 48.3%. In addition to the GSTC co-funding, the consortium provided the domestic natural gas storage industry with a technology transfer and outreach infrastructure. The technology transfer and outreach were conducted by having project mentoring teams and a GSTC website, and by working closely with the Pipeline Research Council International (PRCI) to jointly host technology transfer meetings and occasional field excursions. A total of 15 technology transfer/strategic planning workshops were held.

  2. Interim storage study report

    SciTech Connect (OSTI)

    Rawlins, J.K.

    1998-02-01

    High-level radioactive waste (HLW) stored at the Idaho Chemical Processing Plant (ICPP) in the form of calcine and liquid and liquid sodium-bearing waste (SBW) will be processed to provide a stable waste form and prepare the waste to be transported to a permanent repository. Because a permanent repository will not be available when the waste is processed, the waste must be stored at ICPP in an Interim Storage Facility (ISF). This report documents consideration of an ISF for each of the waste processing options under consideration.

  3. Storage Ring Parameters

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation ofAlbuquerque|SensitiveApril 2,BL4-2StefanLightsource504,103FormulaStorage

  4. Storage Ring Parameters

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation ofAlbuquerque|SensitiveAprilPhoton Source Parameters Storage Ring Parameters

  5. Storage Ring Parameters

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation ofAlbuquerque|SensitiveAprilPhoton Source Parameters Storage Ring

  6. Storage Trends and Summaries

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation ofAlbuquerque|SensitiveAprilPhoton Source Parameters Storage

  7. Storage by Scientific Discipline

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation ofAlbuquerque|SensitiveAprilPhoton Source Parameters StorageHeat & Cool »

  8. Storage Ring Parameters

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust,Field-effect Photovoltaics -7541C.3X-rays3 Prepared by:'!TransportStorage Ring Parameters

  9. Storage Ring Parameters

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust,Field-effect Photovoltaics -7541C.3X-rays3 Prepared by:'!TransportStorage Ring

  10. National Energy Storage Strategy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergyTher i nAand DOEDepartment ofProgram | DepartmentEnergy6 3Energy Storage Strategy

  11. Electricity storage for grid-connected household dwellings with PV panels

    SciTech Connect (OSTI)

    Mulder, Grietus; Six, Daan; Ridder, Fjo De

    2010-07-15

    Classically electricity storage for PV panels is mostly designed for stand-alone applications. In contrast, we focus in this article on houses connected to the grid with a small-scale storage to store a part of the solar power for postponed consumption within the day or the next days. In this way the house owner becomes less dependent on the grid and does only pay for the net shortage of his energy production. Local storage solutions pave the way for many new applications like omitting over-voltage of the line and bridging periods of power-line black-out. Since 2009 using self-consumption of PV energy is publicly encouraged in Germany, which can be realised by electric storage. This paper develops methods to determine the optimal storage size for grid-connected dwellings with PV panels. From measurements in houses we were able to establish calculation rules for sizing the storage. Two situations for electricity storage are covered: - the storage system is an optimum to cover most of the electricity needs; - it is an optimum for covering the peak power need of a dwelling. After these calculation rules a second step is needed to determine the size of the real battery. The article treats the aspects that should be taken into consideration before buying a specific battery like lead-acid and lithium-ion batteries. (author)

  12. Article for thermal energy storage

    DOE Patents [OSTI]

    Salyer, Ival O. (Dayton, OH)

    2000-06-27

    A thermal energy storage composition is provided which is in the form of a gel. The composition includes a phase change material and silica particles, where the phase change material may comprise a linear alkyl hydrocarbon, water/urea, or water. The thermal energy storage composition has a high thermal conductivity, high thermal energy storage, and may be used in a variety of applications such as in thermal shipping containers and gel packs.

  13. Gas hydrate cool storage system

    DOE Patents [OSTI]

    Ternes, M.P.; Kedl, R.J.

    1984-09-12

    The invention presented relates to the development of a process utilizing a gas hydrate as a cool storage medium for alleviating electric load demands during peak usage periods. Several objectives of the invention are mentioned concerning the formation of the gas hydrate as storage material in a thermal energy storage system within a heat pump cycle system. The gas hydrate was formed using a refrigerant in water and an example with R-12 refrigerant is included. (BCS)

  14. Type A Accident Investigation Board Report on the July 1, 2008...

    Office of Environmental Management (EM)

    July 1, 2008, of the Vehicle Fatality Accident-Western Area Power Marketing Administration Type A Accident Investigation Board Report on the July 1, 2008, of the Vehicle Fatality...

  15. Type A Accident Investigation Board Report on the April 3, 1995...

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

    1995 The accident under investigation occurred on April 3, 1995, at approximately 10:46 a.m. As a result of the accident, a Wackenhut Services, Incorporated-Savannah River Site...

  16. The Effect of the 18-Year Old Drinking Age on Auto Accidents

    E-Print Network [OSTI]

    Cucchiaro, Stephen

    The effect of Massachusetts' reduced drinking age on auto accidents is examined by employing an interrupted time series analysis of monthly accident data covering the period January, 1969, through September 1973. The data ...

  17. Accident Analysis and Prevention 42 (2010) 364371 Contents lists available at ScienceDirect

    E-Print Network [OSTI]

    Boggess, May M.

    2010-01-01

    number of studies reported age-specific accident rates for heavy vehicles for the spec- trum of driver' shaped curve indicates a higher risk of accident involvement for both younger and older drivers. More

  18. Utilizing an encroachment probability benefit-cost model to estimate accident reduction factors 

    E-Print Network [OSTI]

    Hayes, Carolyn A

    1997-01-01

    Improving safety on Texas roadways is a major public concern. Over the years, the Texas Department of Transportation and other highway agencies have become interested in reducing society's accident cost while maximizing returns on accident...

  19. Calculation notes for surface leak resulting in pool, TWRS FSAR accident analysis

    SciTech Connect (OSTI)

    Hall, B.W.

    1996-09-25

    This document includes the calculations performed to quantify the risk associated with the unmitigated and mitigated accident scenarios described in the TWRS FSAR for the accident analysis titled: Surface Leaks Resulting in Pool.

  20. Calculation Notes for Subsurface Leak Resulting in Pool, TWRS FSAR Accident Analysis

    SciTech Connect (OSTI)

    Hall, B.W.

    1996-09-25

    This document includes the calculations performed to quantify the risk associated with the unmitigated and mitigated accident scenarios described in the TWRS FSAR for the accident analysis titled: Subsurface Leaks Resulting in Pool.

  1. The Petascale Data Storage Institute

    SciTech Connect (OSTI)

    Gibson, Garth; Long, Darrell; Honeyman, Peter; Grider, Gary; Kramer, William; Shalf, John; Roth, Philip; Felix, Evan; Ward, Lee

    2013-07-01

    Petascale computing infrastructures for scientific discovery make petascale demands on information storage capacity, performance, concurrency, reliability, availability, and manageability.The Petascale Data Storage Institute focuses on the data storage problems found in petascale scientific computing environments, with special attention to community issues such as interoperability, community buy-in, and shared tools.The Petascale Data Storage Institute is a collaboration between researchers at Carnegie Mellon University, National Energy Research Scientific Computing Center, Pacific Northwest National Laboratory, Oak Ridge National Laboratory, Sandia National Laboratory, Los Alamos National Laboratory, University of Michigan, and the University of California at Santa Cruz.

  2. Holographic Storage of Biphoton Entanglement

    E-Print Network [OSTI]

    Han-Ning Dai; Han Zhang; Sheng-Jun Yang; Tian-Ming Zhao; Jun Rui; You-Jin Deng; Li Li; Nai-Le Liu; Shuai Chen; Xiao-Hui Bao; Xian-Min Jin; Bo Zhao; Jian-Wei Pan

    2012-04-06

    Coherent and reversible storage of multi-photon entanglement with a multimode quantum memory is essential for scalable all-optical quantum information processing. Although single photon has been successfully stored in different quantum systems, storage of multi-photon entanglement remains challenging because of the critical requirement for coherent control of photonic entanglement source, multimode quantum memory, and quantum interface between them. Here we demonstrate a coherent and reversible storage of biphoton Bell-type entanglement with a holographic multimode atomic-ensemble-based quantum memory. The retrieved biphoton entanglement violates Bell's inequality for 1 microsecond storage time and a memory-process fidelity of 98% is demonstrated by quantum state tomography.

  3. Energy Storage Laboratory (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2011-10-01

    This fact sheet describes the purpose, lab specifications, applications scenarios, and information on how to partner with NREL's Energy Storage Laboratory at the Energy Systems Integration Facility. At NREL's Energy Storage Laboratory in the Energy Systems Integration Facility (ESIF), research focuses on the integration of energy storage systems (both stationary and vehicle-mounted) and interconnection with the utility grid. Focusing on battery technologies, but also hosting ultra-capacitors and other electrical energy storage technologies, the laboratory will provide all resources necessary to develop, test, and prove energy storage system performance and compatibility with distributed energy systems. The laboratory will also provide robust vehicle testing capability, including a drive-in environmental chamber, which can accommodate commercial-sized hybrid, electric, biodiesel, ethanol, compressed natural gas, and hydrogen fueled vehicles. The Energy Storage Laboratory is designed to ensure personnel and equipment safety when testing hazardous battery systems or other energy storage technologies. Closely coupled with the research electrical distribution bus at ESIF, the Energy Storage Laboratory will offer megawatt-scale power testing capability as well as advanced hardware-in-the-loop and model-in-the-loop simulation capabilities. Some application scenarios are: The following types of tests - Performance, Efficiency, Safety, Model validation, and Long duration reliability. (2) Performed on the following equipment types - (a) Vehicle batteries (both charging and discharging V2G); (b) Stationary batteries; (c) power conversion equipment for energy storage; (d) ultra- and super-capacitor systems; and (e) DC systems, such as commercial microgrids.

  4. Automotive Energy Storage Systems 2015

    Broader source: Energy.gov [DOE]

    Automotive Energy Storage Systems 2015, the ITB Group’s 16th annual technical conference, was held from March 4–5, 2015, in Novi, Michigan.

  5. Transmission Line Security Monitor

    ScienceCinema (OSTI)

    None

    2013-05-28

    The Transmission Line Security Monitor is a multi-sensor monitor that mounts directly on high-voltage transmission lines to detect, characterize and communicate terrorist activity, human tampering and threatening conditions around support towers. For more information about INL's critical infrastructure protection research, visit http://www.facebook.com/idahonationallaboratory.

  6. Transmission Line Security Monitor

    SciTech Connect (OSTI)

    2011-01-01

    The Transmission Line Security Monitor is a multi-sensor monitor that mounts directly on high-voltage transmission lines to detect, characterize and communicate terrorist activity, human tampering and threatening conditions around support towers. For more information about INL's critical infrastructure protection research, visit http://www.facebook.com/idahonationallaboratory.

  7. Identification and evaluation of PWR in-vessel severe accident management strategies

    SciTech Connect (OSTI)

    Dukelow, J S [Pacific Northwest Lab., Richland, WA (United States); Harrison, D G [Jason Associates, Idaho Falls, ID (United States); Morgenstern, M [Battelle Human Affairs Research Center, Seattle, WA (United States)

    1992-03-01

    This reports documents work performed the NRC/RES Accident Management Guidance Program to evaluate possible strategies for mitigating the consequences of PWR severe accidents. The selection and evaluation of strategies was limited to the in-vessel phase of the severe accident, i.e., after the initiation of core degradation and prior to RPV failure. A parallel project at BNL has been considering strategies applicable to the ex-vessel phase of PWR severe accidents.

  8. Relating geometric design consistency and accident experience on two-lane rural highways 

    E-Print Network [OSTI]

    Glascock, Stephen Wade

    1991-01-01

    to provide more efficient transportation on the one hand, and this same compulsion pushes man to work and devise methods of reducing the probability and severity of accidents. For so long as we have humans at the control of the transport vehicle..., the driver, and the vehicle contribute to the occurrence and severity of accidents. Seldom is information included in accident analyses that addresses all of these factors. Even with more complete accident data bases, however, researchers often are unable...

  9. An analysis to determine correlations of freeway traffic accidents with specific geometric design features 

    E-Print Network [OSTI]

    Smith, Frank Miller

    1960-01-01

    was followed to select an accident frequency index was the development and evaluation of several experimental indices. Factors considered, Measurement of accident exposure based on volumes and the number of accidents which occurred served as the basic... of these conditions, the length of the through lanes, in each direction from the ramp terminal, over which accidents were counted was a variable which was considered for several indices. In the application of this factor, through-lane acci- dents were grouped...

  10. Flywheel energy storage workshop

    SciTech Connect (OSTI)

    O`Kain, D.; Carmack, J.

    1995-12-31

    Since the November 1993 Flywheel Workshop, there has been a major surge of interest in Flywheel Energy Storage. Numerous flywheel programs have been funded by the Advanced Research Projects Agency (ARPA), by the Department of Energy (DOE) through the Hybrid Vehicle Program, and by private investment. Several new prototype systems have been built and are being tested. The operational performance characteristics of flywheel energy storage are being recognized as attractive for a number of potential applications. Programs are underway to develop flywheels for cars, buses, boats, trains, satellites, and for electric utility applications such as power quality, uninterruptible power supplies, and load leveling. With the tremendous amount of flywheel activity during the last two years, this workshop should again provide an excellent opportunity for presentation of new information. This workshop is jointly sponsored by ARPA and DOE to provide a review of the status of current flywheel programs and to provide a forum for presentation of new flywheel technology. Technology areas of interest include flywheel applications, flywheel systems, design, materials, fabrication, assembly, safety & containment, ball bearings, magnetic bearings, motor/generators, power electronics, mounting systems, test procedures, and systems integration. Information from the workshop will help guide ARPA & DOE planning for future flywheel programs. This document is comprised of detailed viewgraphs.

  11. Nano- and Microscale Architectures for Energy Storage Systems

    E-Print Network [OSTI]

    Dudek, Lisa

    2014-01-01

    Host for Emerging Energy Storage Systems Introduction Li-ionStorage Systems …………………………………………………………………………………………………………85Architectures for Energy Storage Systems A dissertation

  12. Electrochemical hydrogen Storage Systems

    SciTech Connect (OSTI)

    Dr. Digby Macdonald

    2010-08-09

    As the global need for energy increases, scientists and engineers have found a possible solution by using hydrogen to power our world. Although hydrogen can be combusted as a fuel, it is considered an energy carrier for use in fuel cells wherein it is consumed (oxidized) without the production of greenhouse gases and produces electrical energy with high efficiency. Chemical storage of hydrogen involves release of hydrogen in a controlled manner from materials in which the hydrogen is covalently bound. Sodium borohydride and aminoborane are two materials given consideration as chemical hydrogen storage materials by the US Department of Energy. A very significant barrier to adoption of these materials as hydrogen carriers is their regeneration from 'spent fuel,' i.e., the material remaining after discharge of hydrogen. The U.S. Department of Energy (DOE) formed a Center of Excellence for Chemical Hydrogen Storage, and this work stems from that project. The DOE has identified boron hydrides as being the main compounds of interest as hydrogen storage materials. The various boron hydrides are then oxidized to release their hydrogen, thereby forming a 'spent fuel' in the form of a lower boron hydride or even a boron oxide. The ultimate goal of this project is to take the oxidized boron hydrides as the spent fuel and hydrogenate them back to their original form so they can be used again as a fuel. Thus this research is essentially a boron hydride recycling project. In this report, research directed at regeneration of sodium borohydride and aminoborane is described. For sodium borohydride, electrochemical reduction of boric acid and sodium metaborate (representing spent fuel) in alkaline, aqueous solution has been investigated. Similarly to literature reports (primarily patents), a variety of cathode materials were tried in these experiments. Additionally, approaches directed at overcoming electrostatic repulsion of borate anion from the cathode, not described in the previous literature for electrochemical reduction of spent fuels, have been attempted. A quantitative analytical method for measuring the concentration of sodium borohydride in alkaline aqueous solution has been developed as part of this work and is described herein. Finally, findings from stability tests for sodium borohydride in aqueous solutions of several different compositions are reported. For aminoborane, other research institutes have developed regeneration schemes involving tributyltin hydride. In this report, electrochemical reduction experiments attempting to regenerate tributyltin hydride from tributyltin chloride (a representative by-product of the regeneration scheme) are described. These experiments were performed in the non-aqueous solvents acetonitrile and 1,2-dimethoxyethane. A non-aqueous reference electrode for electrolysis experiments in acetonitrile was developed and is described. One class of boron hydrides, called polyhedral boranes, became of interest to the DOE due to their ability to contain a sufficient amount of hydrogen to meet program goals and because of their physical and chemical safety attributes. Unfortunately, the research performed here has shown that polyhedral boranes do not react in such a way as to allow enough hydrogen to be released, nor do they appear to undergo hydrogenation from the spent fuel form back to the original hydride. After the polyhedral boranes were investigated, the project goals remained the same but the hydrogen storage material was switched by the DOE to ammonia borane. Ammonia borane was found to undergo an irreversible hydrogen release process, so a direct hydrogenation was not able to occur. To achieve the hydrogenation of the spent ammonia borane fuel, an indirect hydrogenation reaction is possible by using compounds called organotin hydrides. In this process, the organotin hydrides will hydrogenate the spent ammonia borane fuel at the cost of their own oxidation, which forms organotin halides. To enable a closed-loop cycle, our task was then to be able to hydrogenate the organotin halides back to th

  13. Accident/Injury Reporting, Investigation, & Basic First Aid Plan

    E-Print Network [OSTI]

    Long, Nicholas

    . It is designed to help reduce injuries by reducing unsafe or hazardous conditions and discouraging accident causing unsafe acts or practices. It applies to all SFASU employees and campus locations conditions to your supervisor and the Safety Department by filling out a Report of Safety or Health Hazard

  14. FORMALISM HELPS IN DESCRIBING ACCIDENTS Peter Ladkin, Universitt Bielefeld, Germany

    E-Print Network [OSTI]

    Ladkin, Peter B.

    , such reasoning engineering is both essential and non-trivial. Accident reports in aviation present careful disagreement systems resulting from maintenance-induced damage leading to the separation of the No. 1 engine maintenance procedures which led to failure of the pylon structure. We shall analyse this statement

  15. An analysis of accident experience at entrance ramps within construction work zones at long-term freeway reconstruction projects in Texas 

    E-Print Network [OSTI]

    Casteel, David Bryan

    1991-01-01

    , severe accidents, daytime accidents, and multi-vehicle accidents (other than rear-end accidents) increased disproportionately in entrance ramp areas during construction. Conversely, accident frequencies did not increase significantly (a =0. 05... in Virginia, found that accidents in construction zones during 1977 were less severe than normal highway accidents. A reported 35 percent of work zone accidents were rear-end collisions. This may have contributed to the decrease in severity of reported work...

  16. Chemical Hydrogen Storage Center Center of Excellence

    E-Print Network [OSTI]

    Carver, Jeffrey C.

    Chemical Hydrogen Storage Center Center of Excellence for Chemical Hydrogen Storage William Tumas proprietary or confidential information #12;2 Chemical Hydrogen Storage Center Overview Project Start Date: FY Barriers Addressed #12;3 Chemical Hydrogen Storage Center Chemical Hydrogen Storage Center National

  17. Assessment of the amount of cesium-137 released into the Pacific Ocean after the Fukushima accident

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Assessment of the amount of cesium-137 released into the Pacific Ocean after the Fukushima accident into the Pacific Ocean after the Fukushima accident and analysis of its dispersion in Japanese coastal waters, J into the ocean from the Fukushima Daiichi nuclear power plant (NPP) after the accident in March 2011 and to gain

  18. Why System Safety Professionals Should Read Accident Reports C. M. Holloway*, C. W. Johnson

    E-Print Network [OSTI]

    Johnson, Chris

    Why System Safety Professionals Should Read Accident Reports C. M. Holloway*, C. W. Johnson *NASA, who regularly read accident reports reap important benefits. These benefits include an improved accident reports regularly. This is a shame. People from many different disciplines have much to gain

  19. K West Basin Integrated Water Treatment System (IWTS) E-F Annular Filter Vessel Accident Calculations

    SciTech Connect (OSTI)

    PIEPHO, M.G.

    2000-01-10

    Four bounding accidents postulated for the K West Basin integrated water treatment system are evaluated against applicable risk evaluation guidelines. The accidents are a spray leak during fuel retrieval, spray leak during backflushing a hydrogen explosion, and a fire breaching filter vessel and enclosure. Event trees and accident probabilities are estimated. In all cases, the unmitigated dose consequences are below the risk evaluation guidelines.

  20. K West Basin Integrated Water Treatment System (IWTS) E-F Annular Filter Vessel Accident Calculations

    SciTech Connect (OSTI)

    RITTMANN, P.D.

    1999-10-07

    Three bounding accidents postdated for the K West Basin integrated water treatment system are evaluated against applicable risk evaluation guidelines. The accidents are a spray leak during fuel retrieval, spray leak during backflushing, and a hydrogen explosion. Event trees and accident probabilities are estimated. In all cases, the unmitigated dose consequences are below the risk evaluation guidelines.

  1. Modelling of Stochastic Hybrid Systems with Applications to Accident Risk Assessment

    E-Print Network [OSTI]

    Del Moral , Pierre

    Modelling of Stochastic Hybrid Systems with Applications to Accident Risk Assessment #12;The SYSTEMS WITH APPLICATIONS TO ACCIDENT RISK ASSESSMENT DISSERTATION to obtain the doctor's degree promotor Prof. dr. A. Bagchi #12;Contents 1 Introduction 3 1.1 Accident risk assessment

  2. Fact Sheet: Tehachapi Wind Energy Storage Project (May 2014)...

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

    Tehachapi Wind Energy Storage Project (May 2014) Fact Sheet: Tehachapi Wind Energy Storage Project (May 2014) The Tehachapi Wind Energy Storage Project (TSP) Battery Energy Storage...

  3. Grid Storage and the Energy Frontier Research Centers | Department...

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

    Grid Storage and the Energy Frontier Research Centers Grid Storage and the Energy Frontier Research Centers DOE: Grid Storage and the Energy Frontier Research Centers Grid Storage...

  4. SENSIBLE HEAT STORAGE FOR A SOLAR THERMAL POWER PLANT

    E-Print Network [OSTI]

    Baldwin, Thomas F.

    2011-01-01

    rates between the gas and the storage unit are specified forcontrol valves. two gas-distribution storage mani- folds andmanifold Main gas compressor Storage manifold Storage flow-

  5. Analysis of the FeCrAl Accident Tolerant Fuel Concept Benefits during BWR Station Blackout Accidents

    SciTech Connect (OSTI)

    Robb, Kevin R

    2015-01-01

    Iron-chromium-aluminum (FeCrAl) alloys are being considered for fuel concepts with enhanced accident tolerance. FeCrAl alloys have very slow oxidation kinetics and good strength at high temperatures. FeCrAl could be used for fuel cladding in light water reactors and/or as channel box material in boiling water reactors (BWRs). To estimate the potential safety gains afforded by the FeCrAl concept, the MELCOR code was used to analyze a range of postulated station blackout severe accident scenarios in a BWR/4 reactor employing FeCrAl. The simulations utilize the most recently known thermophysical properties and oxidation kinetics for FeCrAl. Overall, when compared to the traditional Zircaloy-based cladding and channel box, the FeCrAl concept provides a few extra hours of time for operators to take mitigating actions and/or for evacuations to take place. A coolable core geometry is retained longer, enhancing the ability to stabilize an accident. Finally, due to the slower oxidation kinetics, substantially less hydrogen is generated, and the generation is delayed in time. This decreases the amount of non-condensable gases in containment and the potential for deflagrations to inhibit the accident response.

  6. Nanostructured materials for hydrogen storage

    DOE Patents [OSTI]

    Williamson, Andrew J. (Pleasanton, CA); Reboredo, Fernando A. (Pleasanton, CA)

    2007-12-04

    A system for hydrogen storage comprising a porous nano-structured material with hydrogen absorbed on the surfaces of the porous nano-structured material. The system of hydrogen storage comprises absorbing hydrogen on the surfaces of a porous nano-structured semiconductor material.

  7. Cooperative Repair with Minimum-Storage Regenerating Codes for Distributed Storage

    E-Print Network [OSTI]

    Li, Baochun

    Cooperative Repair with Minimum-Storage Regenerating Codes for Distributed Storage Jun Li, Baochun--Distributed storage systems store redundant data to tolerate failures of storage nodes and lost data should be repaired when storage nodes fail. A class of MDS codes, called minimum- storage regenerating (MSR) codes

  8. March 29, 2008 OS: Mass Storage Structure 1 Mass-Storage Structure

    E-Print Network [OSTI]

    Adam, Salah

    March 29, 2008 OS: Mass Storage Structure 1 Mass-Storage Structure Chapter 12 #12;March 29, 2008 OS: Mass Storage Structure 2 Objectives Describe the physical structure of secondary and tertiary storage of mass-storage devices Discuss operating-system services provided for mass storage, including RAID

  9. Coherent soliton communication lines

    SciTech Connect (OSTI)

    Yushko, O. V. Redyuk, A. A.; Fedoruk, M. P.; Turitsyn, S. K.

    2014-11-15

    The data transmission in coherent fiber-optical communication lines using solitons with a variable phase is studied. It is shown that nonlinear coherent structures (solitons) can be applied for effective signal transmission over a long distance using amplitude and optical-phase keying of information. The optimum ratio of the pulse width to the bit slot at which the spectral efficiency (transmitted bits per second and hertz) is maximal is determined. It is shown that soliton fiber-optical communication lines can ensure data transmission at a higher spectral efficiency as compared to traditional communication lines and at a high signal-to-noise ratio.

  10. Core assembly storage structure

    DOE Patents [OSTI]

    Jones, Jr., Charles E. (Northridge, CA); Brunings, Jay E. (Chatsworth, CA)

    1988-01-01

    A structure for the storage of core assemblies from a liquid metal-cooled nuclear reactor. The structure comprises an enclosed housing having a substantially flat horizontal top plate, a bottom plate and substantially vertical wall members extending therebetween. A plurality of thimble members extend downwardly through the top plate. Each thimble member is closed at its bottom end and has an open end adjacent said top plate. Each thimble member has a length and diameter greater than that of the core assembly to be stored therein. The housing is provided with an inlet duct for the admission of cooling air and an exhaust duct for the discharge of air therefrom, such that when hot core assemblies are placed in the thimbles, the heat generated will by convection cause air to flow from the inlet duct around the thimbles and out the exhaust duct maintaining the core assemblies at a safe temperature without the necessity of auxiliary powered cooling equipment.

  11. Superconducting energy storage

    SciTech Connect (OSTI)

    Giese, R.F.

    1993-10-01

    This report describes the status of energy storage involving superconductors and assesses what impact the recently discovered ceramic superconductors may have on the design of these devices. Our description is intended for R&D managers in government, electric utilities, firms, and national laboratories who wish an overview of what has been done and what remains to be done. It is assumed that the reader is acquainted with superconductivity, but not an expert on the topics discussed here. Indeed, it is the author`s aim to enable the reader to better understand the experts who may ask for the reader`s attention, support, or funding. This report may also inform scientists and engineers who, though expert in related areas, wish to have an introduction to our topic.

  12. Reversible hydrogen storage materials

    DOE Patents [OSTI]

    Ritter, James A. (Lexington, SC); Wang, Tao (Columbia, SC); Ebner, Armin D. (Lexington, SC); Holland, Charles E. (Cayce, SC)

    2012-04-10

    In accordance with the present disclosure, a process for synthesis of a complex hydride material for hydrogen storage is provided. The process includes mixing a borohydride with at least one additive agent and at least one catalyst and heating the mixture at a temperature of less than about 600.degree. C. and a pressure of H.sub.2 gas to form a complex hydride material. The complex hydride material comprises MAl.sub.xB.sub.yH.sub.z, wherein M is an alkali metal or group IIA metal, Al is the element aluminum, x is any number from 0 to 1, B is the element boron, y is a number from 0 to 13, and z is a number from 4 to 57 with the additive agent and catalyst still being present. The complex hydride material is capable of cyclic dehydrogenation and rehydrogenation and has a hydrogen capacity of at least about 4 weight percent.

  13. On Storage Rings for Short Wavelength FELs

    E-Print Network [OSTI]

    Chattopadhyay, S.

    2010-01-01

    for a hypothetical 144 m long storage ring optimized for FELin the Proceedings On Storage Rings for Short WavelengthLBL-28483 ESG Note-92 ON STORAGE RINGS FOR SHORT WAVELENGTH

  14. Hopper File Storage and I/O

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

    File Storage and IO File Storage and IO Disk Quota Change Request Form Hopper File Systems Hopper has 5 user file systems which provide different degrees of storage, performance...

  15. Storage Viability and Optimization Web Service

    E-Print Network [OSTI]

    Stadler, Michael

    2010-01-01

    of Heat and Electricity Storage and Reliability on MicrogridEPRI-DOE Handbook of Energy Storage for Transmission andLong- vs. Short-Term Energy Storage Technologies Analysis, A

  16. THERMAL ENERGY STORAGE IN AQUIFERS WORKSHOP

    E-Print Network [OSTI]

    Authors, Various

    2011-01-01

    Resources Res. 14: 273-280. THERMAL STORAGE OF COLD WATER INR.C. HARE, 1972. Thermal Storage for Eco-Energy Utilities,W.J. MASICA, 1977. "Thermal Storage for Electric Utilities,"

  17. AQUIFER THERMAL ENERGY STORAGE-A SURVEY

    E-Print Network [OSTI]

    Tsang, Chin Fu

    2012-01-01

    R. C. 1 1972 1 Thermal storage for eco=energy utilities: GE-and Harris, w. B. 0 1978 0 Thermal storage of cold water induration EXPERIMENTS Thermal storage radius (m) thickness

  18. Nanostructured Materials for Energy Generation and Storage

    E-Print Network [OSTI]

    Khan, Javed Miller

    2012-01-01

    energy generation and battery storage via the use ofenergy generation and battery storage via the use of nanos-and storage (e.g lithium-ion rechargeable battery)

  19. Storage Water Heaters | Department of Energy

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

    Storage Water Heaters Storage Water Heaters June 15, 2012 - 6:00pm Addthis Consider energy efficiency when selecting a conventional storage water heater to avoid paying more over...

  20. THERMAL ENERGY STORAGE IN AQUIFERS WORKSHOP

    E-Print Network [OSTI]

    Authors, Various

    2011-01-01

    20) E. B. Quale. Seasonal storage of thermal energy in waterE.B. , 1976. "Seasonal Storage of Thermal Energy in Water ina truly worthwhile goal. Seasonal Storage of Thermal Energy

  1. Functional Carbon Materials for Electrochemical Energy Storage

    E-Print Network [OSTI]

    Zhou, Huihui

    2015-01-01

    Temperature Dense Phase Hydrogen Storage Materials withinJugroot, Review of hydrogen storage techniques for on boardFigure 1.2 Plot of hydrogen storage materials as a function

  2. AQUIFER THERMAL ENERGY STORAGE-A SURVEY

    E-Print Network [OSTI]

    Tsang, Chin Fu

    2012-01-01

    aquifers for heat storage, solar captors for heat productionZakhidov, R. A. 8 1971, Storage of solar energy in a sandy-thermal energy storage for cogeneration and solar systems,

  3. THERMAL ENERGY STORAGE IN AQUIFERS WORKSHOP

    E-Print Network [OSTI]

    Authors, Various

    2011-01-01

    associat~ ed with solar thermal storage. Now this system canand R.A. Zakhidov, "Storage of Solar Energy in a Sandy-Heat as Related to the Storage of Solar Energy. Sharing the

  4. Numerical Simulations of Leakage from Underground LPG Storage Caverns

    SciTech Connect (OSTI)

    Yamamoto, Hajime; Pruess, Karsten

    2004-09-01

    To secure a stable supply of petroleum gas, underground storage caverns for liquified petroleum gas (LPG) are commonly used in many countries worldwide. Storing LPG in underground caverns requires that the surrounding rock mass remain saturated with groundwater and that the water pressure be higher than the liquid pressure inside the cavern. In previous studies, gas containment criteria for underground gas storage based on hydraulic gradient and pressure have been discussed, but these studies do not consider the physicochemical characteristics and behavior of LPG such as vaporization and dissolution in groundwater. Therefore, while these studies are very useful for designing storage caverns, they do not provide better understanding of the either the environmental effects of gas contamination or the behavior of vaporized LPG. In this study, we have performed three-phase fluid flow simulations of gas leakage from underground LPG storage caverns, using the multiphase multicomponent nonisothermal simulator TMVOC (Pruess and Battistelli, 2002), which is capable of solving the three-phase nonisothermal flow of water, gas, and a multicomponent mixture of volatile organic chemicals (VOCs) in multidimensional heterogeneous porous media. A two-dimensional cross-sectional model resembling an actual underground LPG facility in Japan was developed, and gas leakage phenomena were simulated for three different permeability models: (1) a homogeneous model, (2) a single-fault model, and (3) a heterogeneous model. In addition, the behavior of stored LPG was studied for the special case of a water curtain suddenly losing its function because of operational problems, or because of long-term effects such as clogging of boreholes. The results of the study indicate the following: (1) The water curtain system is a very powerful means for preventing gas leakage from underground storage facilities. By operating with appropriate pressure and layout, gas containment can be ensured. (2) However , in highly heterogeneous media such as fractured rock and fault zones, local flow paths within which the gas containment criterion is not satisfied could be formed. To eliminate such zones, treatments such as pre/post grouting or an additional installment of water-curtain boreholes are essential. (3) Along highly conductive features such as faults, even partially saturated zones possess certain effects that can retard or prevent gas leakage, while a fully unsaturated fault connected to the storage cavern can quickly cause a gas blowout. This possibility strongly suggests that ensuring water saturation of the rock surrounding the cavern is a very important requirement. (4) Even if an accident should suddenly impair the water curtain, the gas plume does not quickly penetrate the ground surface. In these simulations, the plume takes several months to reach the ground surface.

  5. Type B Accident Investigation Board Report of the January 20, 1998, Electrical Accident at the Casa Grande Substation,South of Phoenix, Arizona

    Broader source: Energy.gov [DOE]

    This report is an independent product of the Type-B Accident Investigation Board appointed by Michael S.Cowan, Chief Program Officer, Western Area Power Administration.

  6. An accident analysis of the physical plant of the Agricultural and Mechanical College of Texas 

    E-Print Network [OSTI]

    Allen, Gary James

    1963-01-01

    to reduce the fre- quency and/or severity of future accidents. 2 I. THE PROBLEM Statement of the problem. The problem was to make an analysis of the accident records of the Physical Plant Department National Safety Council, Accident Prevention Manual..., based on the analysis of rollected data, as to what type and where safety coz zectiors were most needed to reduce the frequency az d/or severity of accidents. Significance of the problem. The importance of accident prevention was probably best...

  7. Canister storage building (CSB) safety analysis report phase 3: Safety analysis documentation supporting CSB construction

    SciTech Connect (OSTI)

    Garvin, L.J.

    1997-04-28

    The Canister Storage Building (CSB) will be constructed in the 200 East Area of the U.S. Department of Energy (DOE) Hanford Site. The CSB will be used to stage and store spent nuclear fuel (SNF) removed from the Hanford Site K Basins. The objective of this chapter is to describe the characteristics of the site on which the CSB will be located. This description will support the hazard analysis and accident analyses in Chapter 3.0. The purpose of this report is to provide an evaluation of the CSB design criteria, the design's compliance with the applicable criteria, and the basis for authorization to proceed with construction of the CSB.

  8. Power line detection system

    DOE Patents [OSTI]

    Latorre, V.R.; Watwood, D.B.

    1994-09-27

    A short-range, radio frequency (RF) transmitting-receiving system that provides both visual and audio warnings to the pilot of a helicopter or light aircraft of an up-coming power transmission line complex. Small, milliwatt-level narrowband transmitters, powered by the transmission line itself, are installed on top of selected transmission line support towers or within existing warning balls, and provide a continuous RF signal to approaching aircraft. The on-board receiver can be either a separate unit or a portion of the existing avionics, and can also share an existing antenna with another airborne system. Upon receipt of a warning signal, the receiver will trigger a visual and an audio alarm to alert the pilot to the potential power line hazard. 4 figs.

  9. Mitigation of Severe Accident Consequences Using Inherent Safety Principles

    SciTech Connect (OSTI)

    R. A. Wigeland; J. E. Cahalan

    2009-12-01

    Sodium-cooled fast reactors are designed to have a high level of safety. Events of high probability of occurrence are typically handled without consequence through reliable engineering systems and good design practices. For accidents of lower probability, the initiating events are characterized by larger and more numerous challenges to the reactor system, such as failure of one or more major engineered systems and can also include a failure to scram the reactor in response. As the initiating conditions become more severe, they have the potential for creating serious consequences of potential safety significance, including fuel melting, fuel pin disruption and recriticality. If the progression of such accidents is not mitigated by design features of the reactor, energetic events and dispersal of radioactive materials may result. For severe accidents, there are several approaches that can be used to mitigate the consequences of such severe accident initiators, which typically include fuel pin failures and core disruption. One approach is to increase the reliability of the reactor protection system so that the probability of an ATWS event is reduced to less than 1 x 10-6 per reactor year, where larger accident consequences are allowed, meeting the U.S. NRC goal of relegating such accident consequences as core disruption to these extremely low probabilities. The main difficulty with this approach is to convincingly test and guarantee such increased reliability. Another approach is to increase the redundancy of the reactor scram system, which can also reduce the probability of an ATWS event to a frequency of less than 1 x 10-6 per reactor year or lower. The issues with this approach are more related to reactor core design, with the need for a greater number of control rod positions in the reactor core and the associated increase in complexity of the reactor protection system. A third approach is to use the inherent reactivity feedback that occurs in a fast reactor to automatically respond to the change in reactor conditions and to result in a benign response to these events. This approach has the advantage of being relatively simple to implement, and does not face the issue of reliability since only fundamental physical phenomena are used in a passive manner, not active engineered systems. However, the challenge is to present a convincing case that such passive means can be implemented and used. The purpose of this paper is to describe this third approach in detail, the technical basis and experimental validation for the approach, and the resulting reactor performance that can be achieved for ATWS events.

  10. Molecular cytogenetic characterization of a human thyroid cancercell line

    SciTech Connect (OSTI)

    Weier, Heinz-Ulrich G.; Tuton, Tiffany B.; Ito, Yuko; Chu, LisaW.; Lu, Chung-Mei; Baumgartner, Adolf; Zitzelsberger, Horst F.; Weier,Jingly F.

    2006-01-04

    The incidence of papillary thyroid carcinoma (PTC) increases significantly after exposure of the head and neck region to ionizing radiation, yet we know neither the steps involved in malignant transformation of thyroid epithelium nor the specific carcinogenic mode of action of radiation. Such increased tumor frequency became most evident in children after the 1986 nuclear accident in Chernobyl, Ukraine. In the twelve years following the accident, the average incidence of childhood PTCs (chPTC) increased over one hundred-fold compared to the rate of about 1 tumor incidence per 10{sup 6} children per year prior to 1986. To study the etiology of radiation-induced thyroid cancer, we formed an international consortium to investigate chromosomal changes and altered gene expression in cases of post-Chernobyl chPTC. Our approach is based on karyotyping of primary cultures established from chPTC specimens, establishment of cell lines and studies of genotype-phenotype relationships through high resolution chromosome analysis, DNA/cDNA micro-array studies, and mouse xenografts that test for tumorigenicity. Here, we report the application of fluorescence in situ hybridization (FISH)-based techniques for the molecular cytogenetic characterization of a highly tumorigenic chPTC cell line, S48TK, and its subclones. Using chromosome 9 rearrangements as an example, we describe a new approach termed ''BAC-FISH'' to rapidly delineate chromosomal breakpoints, an important step towards a better understanding of the formation of translocations and their functional consequences.

  11. Loss of feed flow, steam generator tube rupture and steam line break thermohydraulic experiments

    SciTech Connect (OSTI)

    Mendler, O J; Takeuchi, K; Young, M Y

    1986-10-01

    The Westinghouse Model Boiler No. 2 (MB-2) steam generator test model at the Engineering Test Facility in Tampa, Florida, was reinstrumented and modified for performing a series of tests simulating steam generator accident transients. The transients simulated were: loss of feed flow, steam generator tube rupture, and steam line break events. This document presents a description of (1) the model boiler and the associated test facility, (2) the tests performed, and (3) the analyses of the test results.

  12. Hydrogen Compression, Storage, and Dispensing Cost Reduction...

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

    Publications 2013 Hydrogen Compression, Storage, and Dispensing Cost Reduction Workshop Final Report Storage - Challenges and Opportunities Hydro-Pac Inc., A High Pressure Company...

  13. Webinar Presentation: Energy Storage Solutions for Microgrids...

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

    Webinar Presentation: Energy Storage Solutions for Microgrids (November 2012) Webinar Presentation: Energy Storage Solutions for Microgrids (November 2012) On November 7, 2012,...

  14. Fact Sheet: Energy Storage Technology Advancement Partnership...

    Energy Savers [EERE]

    More Documents & Publications Webinar Presentation: Energy Storage Solutions for Microgrids (November 2012) Energy Storage Systems 2014 Peer Review Presentations - Session 11...

  15. Integrated Renewable Energy and Energy Storage Systems

    E-Print Network [OSTI]

    Integrated Renewable Energy and Energy Storage Systems Prepared for the U.S. Department of Energy and Energy Storage Systems TABLE OF CONTENTS 1

  16. Energy Storage Systems 2010 Update Conference Presentations ...

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

    Conference Presentations - Day 1, Session 1 Energy Storage Systems 2010 Update Conference Presentations - Day 1, Session 1 The U.S. DOE Energy Storage Systems Program (ESS)...

  17. Analytic Challenges to Valuing Energy Storage

    SciTech Connect (OSTI)

    Ma, Ookie; O'Malley, Mark; Cheung, Kerry; Larochelle, Philippe; Scheer, Rich

    2011-10-25

    Electric grid energy storage value. System-level asset focus for mechanical and electrochemical energy storage. Analysis questions for power system planning, operations, and customer-side solutions.

  18. National Hydrogen Storage Project | Department of Energy

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

    National Hydrogen Storage Project National Hydrogen Storage Project In July 2003, the Department of Energy (DOE) issued a "Grand Challenge" to the global scientific community for...

  19. Hydrogen Storage Materials Workshop Proceedings Workshop, October...

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

    Proceedings Workshop, October 16th, 2002 Hydrogen Storage Materials Workshop Proceedings Workshop, October 16th, 2002 A workshop on compressed and liquefied hydrogen storage was a...

  20. Overview of Gridscale Rampable Intermittent Dispatchable Storage...

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

    in Washington, DC. flowcells2012johnson.pdf More Documents & Publications Energy Storage Systems 2010 Update Conference Presentations - Day 1, Session 1 Energy Storage Systems...

  1. THERMAL ENERGY STORAGE IN AQUIFERS WORKSHOP

    E-Print Network [OSTI]

    Authors, Various

    2011-01-01

    A New Concept in Electric Generation and Energy Storage,"A New Concept in Electric Generation and Energy Storage,"of Solar Energy for Electric Power Generation," Proceedings

  2. Hydrogen Storage - Current Technology | Department of Energy

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

    Fuel Cell Technologies Office Hydrogen Production Hydrogen Delivery Hydrogen Storage Basics Current Technology Gaseous and Liquid Hydrogen Storage Materials-Based Hydrogen...

  3. DRAFT "Energy Advisory Committee" - Energy Storage Subcommittee...

    Energy Savers [EERE]

    Report: Revision 2 DRAFT "Energy Advisory Committee" - Energy Storage Subcommittee Report: Revision 2 Energy storage plays a vital role in all forms of business and affects the...

  4. Energy Storage Systems 2010 Update Conference Presentations ...

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

    Superconducting Magnetic Bearing - Mike Strasik, Boeing.pdf More Documents & Publications Energy Storage Systems 2006 Peer Review - Day 1 morning presentations Energy Storage...

  5. EIA - Analysis of Natural Gas Storage

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    Prices This presentation provides information about EIA's estimates of working gas peak storage capacity, and the development of the natural gas storage industry....

  6. Combinatorial Approach for Hydrogen Storage Materials (presentation...

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

    Approach for Hydrogen Storage Materials (presentation) Combinatorial Approach for Hydrogen Storage Materials (presentation) Presented at the U.S. Department of Energy's Hydrogen...

  7. Energy Storage Systems 2010 Update Conference Presentations ...

    Energy Savers [EERE]

    Electricity Storage - Sanjoy Banerjee, CUNY.pdf PDF icon ESS 2010 Update Conference - Hydrogen-Bromine Flow Batteries for Grid-Scale Energy Storage - Venkat Srinivasan,...

  8. THERMAL ENERGY STORAGE IN AQUIFERS WORKSHOP

    E-Print Network [OSTI]

    Authors, Various

    2011-01-01

    Scale Thermal Energy Storage for Cogeneration and Solarsolar captors, thermal effluents, low cost energy duringSeale Thermal Energy Storage for Cogeneration and Solar

  9. Migrating enterprise storage applications to the cloud

    E-Print Network [OSTI]

    Vrable, Michael Daniel

    2011-01-01

    2.1 Cloud Providers . . . . . . . . . . . .2.1.1 Cloud Storage . . . . . . . . .2.1.2 Cloud Computation . . . . . . 2.2 Enterprise Storage

  10. Carbon Capture and Storage

    SciTech Connect (OSTI)

    Friedmann, S

    2007-10-03

    Carbon capture and sequestration (CCS) is the long-term isolation of carbon dioxide from the atmosphere through physical, chemical, biological, or engineered processes. This includes a range of approaches including soil carbon sequestration (e.g., through no-till farming), terrestrial biomass sequestration (e.g., through planting forests), direct ocean injection of CO{sub 2} either onto the deep seafloor or into the intermediate depths, injection into deep geological formations, or even direct conversion of CO{sub 2} to carbonate minerals. Some of these approaches are considered geoengineering (see the appropriate chapter herein). All are considered in the 2005 special report by the Intergovernmental Panel on Climate Change (IPCC 2005). Of the range of options available, geological carbon sequestration (GCS) appears to be the most actionable and economic option for major greenhouse gas reduction in the next 10-30 years. The basis for this interest includes several factors: (1) The potential capacities are large based on initial estimates. Formal estimates for global storage potential vary substantially, but are likely to be between 800 and 3300 Gt of C (3000 and 10,000 Gt of CO{sub 2}), with significant capacity located reasonably near large point sources of the CO{sub 2}. (2) GCS can begin operations with demonstrated technology. Carbon dioxide has been separated from large point sources for nearly 100 years, and has been injected underground for over 30 years (below). (3) Testing of GCS at intermediate scale is feasible. In the US, Canada, and many industrial countries, large CO{sub 2} sources like power plants and refineries lie near prospective storage sites. These plants could be retrofit today and injection begun (while bearing in mind scientific uncertainties and unknowns). Indeed, some have, and three projects described here provide a great deal of information on the operational needs and field implementation of CCS. Part of this interest comes from several key documents written in the last three years that provide information on the status, economics, technology, and impact of CCS. These are cited throughout this text and identified as key references at the end of this manuscript. When coupled with improvements in energy efficiency, renewable energy supplies, and nuclear power, CCS help dramatically reduce current and future emissions (US CCTP 2005, MIT 2007). If CCS is not available as a carbon management option, it will be much more difficult and much more expensive to stabilize atmospheric CO{sub 2} emissions. Recent estimates put the cost of carbon abatement without CCS to be 30-80% higher that if CCS were to be available (Edmonds et al. 2004).

  11. Transmission line capital costs

    SciTech Connect (OSTI)

    Hughes, K.R.; Brown, D.R.

    1995-05-01

    The displacement or deferral of conventional AC transmission line installation is a key benefit associated with several technologies being developed with the support of the U.S. Department of Energy`s Office of Energy Management (OEM). Previous benefits assessments conducted within OEM have been based on significantly different assumptions for the average cost per mile of AC transmission line. In response to this uncertainty, an investigation of transmission line capital cost data was initiated. The objective of this study was to develop a database for preparing preliminary estimates of transmission line costs. An extensive search of potential data sources identified databases maintained by the Bonneville Power Administration (BPA) and the Western Area Power Administration (WAPA) as superior sources of transmission line cost data. The BPA and WAPA data were adjusted to a common basis and combined together. The composite database covers voltage levels from 13.8 to 765 W, with cost estimates for a given voltage level varying depending on conductor size, tower material type, tower frame type, and number of circuits. Reported transmission line costs vary significantly, even for a given voltage level. This can usually be explained by variation in the design factors noted above and variation in environmental and land (right-of-way) costs, which are extremely site-specific. Cost estimates prepared from the composite database were compared to cost data collected by the Federal Energy Regulatory Commission (FERC) for investor-owned utilities from across the United States. The comparison was hampered because the only design specifications included with the FERC data were voltage level and line length. Working within this limitation, the FERC data were not found to differ significantly from the composite database. Therefore, the composite database was judged to be a reasonable proxy for estimating national average costs.

  12. Enhanced Accident Tolerant LWR Fuels National Metrics Workshop Report

    SciTech Connect (OSTI)

    Lori Braase

    2013-01-01

    The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), in collaboration with the nuclear industry, has been conducting research and development (R&D) activities on advanced Light Water Reactor (LWR) fuels for the last few years. The emphasis for these activities was on improving the fuel performance in terms of increased burnup for waste minimization and increased power density for power upgrades, as well as collaborating with industry on fuel reliability. After the events at the Fukushima Nuclear Power Plant in Japan in March 2011, enhancing the accident tolerance of LWRs became a topic of serious discussion. In the Consolidated Appropriations Act, 2012, Conference Report 112-75, the U.S. Congress directed DOE-NE to: • Give “priority to developing enhanced fuels and cladding for light water reactors to improve safety in the event of accidents in the reactor or spent fuel pools.” • Give “special technical emphasis and funding priority…to activities aimed at the development and near-term qualification of meltdown-resistant, accident-tolerant nuclear fuels that would enhance the safety of present and future generations of light water reactors.” • Report “to the Committee, within 90 days of enactment of this act, on its plan for development of meltdown-resistant fuels leading to reactor testing and utilization by 2020.” Fuels with enhanced accident tolerance are those that, in comparison with the standard UO2-zirconium alloy system currently used by the nuclear industry, can tolerate loss of active cooling in the reactor core for a considerably longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations, and operational transients, as well as design-basis and beyond design-basis events. The overall draft strategy for development and demonstration is comprised of three phases: Feasibility Assessment and Down-selection; Development and Qualification; and Commercialization. The activities performed during the feasibility assessment phase include laboratory scale experiments; fuel performance code updates; and analytical assessment of economic, operational, safety, fuel cycle, and environmental impacts of the new concepts. The development and qualification stage will consist of fuel fabrication and large scale irradiation and safety basis testing, leading to qualification and ultimate NRC licensing of the new fuel. The commercialization phase initiates technology transfer to industry for implementation. Attributes for fuels with enhanced accident tolerance include improved reaction kinetics with steam and slower hydrogen generation rate, while maintaining acceptable cladding thermo-mechanical properties; fuel thermo-mechanical properties; fuel-clad interactions; and fission-product behavior. These attributes provide a qualitative guidance for parameters that must be considered in the development of fuels and cladding with enhanced accident tolerance. However, quantitative metrics must be developed for these attributes. To initiate the quantitative metrics development, a Light Water Reactor Enhanced Accident Tolerant Fuels Metrics Development Workshop was held October 10-11, 2012, in Germantown, Maryland. This document summarizes the structure and outcome of the two-day workshop. Questions regarding the content can be directed to Lori Braase, 208-526-7763, lori.braase@inl.gov.

  13. The Nevada railroad system: Physical, operational, and accident characteristics

    SciTech Connect (OSTI)

    1991-09-01

    This report provides a description of the operational and physical characteristics of the Nevada railroad system. To understand the dynamics of the rail system, one must consider the system`s physical characteristics, routing, uses, interactions with other systems, and unique operational characteristics, if any. This report is presented in two parts. The first part is a narrative description of all mainlines and major branchlines of the Nevada railroad system. Each Nevada rail route is described, including the route`s physical characteristics, traffic type and volume, track conditions, and history. The second part of this study provides a more detailed analysis of Nevada railroad accident characteristics than was presented in the Preliminary Nevada Transportation Accident Characterization Study (DOE, 1990).

  14. ADVANCED UNDERGROUND GAS STORAGE CONCEPTS REFRIGERATED-MINED CAVERN STORAGE

    SciTech Connect (OSTI)

    1998-09-01

    Limited demand and high cost has prevented the construction of hard rock caverns in this country for a number of years. The storage of natural gas in mined caverns may prove technically feasible if the geology of the targeted market area is suitable; and economically feasible if the cost and convenience of service is competitive with alternative available storage methods for peak supply requirements. It is believed that mined cavern storage can provide the advantages of high delivery rates and multiple fill-withdrawal cycles in areas where salt cavern storage is not possible. In this research project, PB-KBB merged advanced mining technologies and gas refrigeration techniques to develop conceptual designs and cost estimates to demonstrate the commercialization potential of the storage of refrigerated natural gas in hard rock caverns. Five regions of the U.S.A. were studied for underground storage development and PB-KBB reviewed the literature to determine if the geology of these regions was suitable for siting hard rock storage caverns. Area gas market conditions in these regions were also studied to determine the need for such storage. Based on an analysis of many factors, a possible site was determined to be in Howard and Montgomery Counties, Maryland. The area has compatible geology and a gas industry infrastructure for the nearby market populous of Baltimore and Washington D.C.. As Gas temperature is lowered, the compressibility of the gas reaches an optimum value. The compressibility of the gas, and the resultant gas density, is a function of temperature and pressure. This relationship can be used to commercial advantage by reducing the size of a storage cavern for a given working volume of natural gas. This study looks at this relationship and and the potential for commercialization of the process in a storage application. A conceptual process design, and cavern design were developed for various operating conditions. Potential site locations were considered and a typical plant layout was developed. In addition a geomechanical review of the proposed cavern design was performed, evaluating the stability of the mine rooms and shafts, and the effects of the refrigerated gas temperatures on the stability of the cavern. Capital and operating cost estimates were also developed for the various temperature cases considered. The cost estimates developed were used to perform a comparative market analysis of this type of gas storage system to other systems that are commercially used in the region of the study.

  15. REQUIREMENTS AND GUIDELINES FOR NSLS EXPERIMENTAL BEAM LINE VACUUM SYSTEMS-REVISION B.

    SciTech Connect (OSTI)

    FOERSTER,C.

    1999-05-01

    Typical beam lines are comprised of an assembly of vacuum valves and shutters referred to as a ''front end'', optical elements to monochromatize, focus and split the photon beam, and an experimental area where a target sample is placed into the photon beam and data from the interaction is detected and recorded. Windows are used to separate sections of beam lines that are not compatible with storage ring ultra high vacuum. Some experimental beam lines share a common vacuum with storage rings. Sections of beam lines are only allowed to vent up to atmospheric pressure using pure nitrogen gas after a vacuum barrier is established to protect ring vacuum. The front end may only be bled up when there is no current in the machine. This is especially true on the VUV storage ring where for most experiments, windows are not used. For the shorter wavelength, more energetic photons of the x-ray ring, beryllium windows are used at various beam line locations so that the monochromator, mirror box or sample chamber may be used in a helium atmosphere or rough vacuum. The window separates ring vacuum from the environment of the downstream beam line components. The stored beam lifetime in the storage rings and the maintenance of desirable reflection properties of optical surfaces depend upon hydrocarbon-free, ultra-high vacuum systems. Storage ring vacuum systems will operate at pressures of {approximately} 1 x 10{sup {minus}10} Torr without beam and {approximately} 1 x 10{sup {minus}9} Torr with beam. Systems are free of hydrocarbons in the sense that no pumps, valves, etc. containing organics are used. Components are all-metal, chemically cleaned and bakeable. To the extent that beam lines share a common vacuum with the storage ring, the same criteria will hold for beam line components. The design philosophy for NSLS beam lines is to use all-metal, hydrocarbon-free front end components and recommend that experimenters use this approach for common vacuum hardware downstream of front ends. O-ring-sealed valves, if used, are not permitted upstream of the monochromator exit aperture. It will be the responsibility of users to demonstrate that their experiment will not degrade the pressure or quality of the storage ring vacuum. As a matter of operating policy, all beam lines will be monitored for prescribed pressure and the contribution of high mass gases to this pressure each time a beam line has been opened to ring vacuum.

  16. Markov Model of Severe Accident Progression and Management

    SciTech Connect (OSTI)

    Bari, R.A.; Cheng, L.; Cuadra,A.; Ginsberg,T.; Lehner,J.; Martinez-Guridi,G.; Mubayi,V.; Pratt,W.T.; Yue, M.

    2012-06-25

    The earthquake and tsunami that hit the nuclear power plants at the Fukushima Daiichi site in March 2011 led to extensive fuel damage, including possible fuel melting, slumping, and relocation at the affected reactors. A so-called feed-and-bleed mode of reactor cooling was initially established to remove decay heat. The plan was to eventually switch over to a recirculation cooling system. Failure of feed and bleed was a possibility during the interim period. Furthermore, even if recirculation was established, there was a possibility of its subsequent failure. Decay heat has to be sufficiently removed to prevent further core degradation. To understand the possible evolution of the accident conditions and to have a tool for potential future hypothetical evaluations of accidents at other nuclear facilities, a Markov model of the state of the reactors was constructed in the immediate aftermath of the accident and was executed under different assumptions of potential future challenges. This work was performed at the request of the U.S. Department of Energy to explore 'what-if' scenarios in the immediate aftermath of the accident. The work began in mid-March and continued until mid-May 2011. The analysis had the following goals: (1) To provide an overall framework for describing possible future states of the damaged reactors; (2) To permit an impact analysis of 'what-if' scenarios that could lead to more severe outcomes; (3) To determine approximate probabilities of alternative end-states under various assumptions about failure and repair times of cooling systems; (4) To infer the reliability requirements of closed loop cooling systems needed to achieve stable core end-states and (5) To establish the importance for the results of the various cooling system and physical phenomenological parameters via sensitivity calculations.

  17. Ion irradiation testing of Improved Accident Tolerant Cladding Materials

    SciTech Connect (OSTI)

    Anderoglu, Osman [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Tesmer, Joseph R. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Maloy, Stuart A. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-01-14

    This report summarizes the results of ion irradiations conducted on two FeCrAl alloys (named as ORNL A&B) for improving the accident tolerance of LWR nuclear fuel cladding. After irradiation with 1.5 MeV protons to ~0.5 to ~1 dpa and 300°C nanoindentations were performed on the cross-sections along the ion range. An increase in hardness was observed in both alloys. Microstructural analysis shows radiation induced defects.

  18. TABLE OF CONTENTS Accident Prevention Signs, Tags, Labels, Signals,

    E-Print Network [OSTI]

    US Army Corps of Engineers

    to meet or exceed ANSI and/or OSHA requirements. USACE facilities shall use signs based upon and contractors may opt to use signs meeting either the OSHA or ANSI standards for temporary use during the life.200; Accident Prevention Signs and Tags; e. ANSI/IEEE C95.2; f. ANSI Z136.1; g. ANSI Z535.1; h. ANSI Z535.2; i

  19. Phase II Accident Investigation Board Briefing | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankADVANCED MANUFACTURINGEnergy Bills andOrder 422.1, CONDUCTCritical Materials UsePhase II Accident

  20. Conductive lithium storage electrode

    DOE Patents [OSTI]

    Chiang, Yet-Ming; Chung, Sung-Yoon; Bloking, Jason T; Andersson, Anna M

    2014-10-07

    A compound comprising a composition A.sub.x(M'.sub.1-aM''.sub.a).sub.y(XD.sub.4).sub.z, A.sub.x(M'.sub.1-aM''.sub.a).sub.y(DXD.sub.4).sub.z, or A.sub.x(M'.sub.1-aM''.sub.a).sub.y(X.sub.2D.sub.7).sub.z, (A.sub.1-aM''.sub.a).sub.xM'.sub.y(XD.sub.4).sub.z, (A.sub.1-aM''.sub.a).sub.xM'.sub.y(DXD.sub.4).sub.z, or (A.sub.1-aM''.sub.a).sub.xM'.sub.y(X.sub.2D.sub.7).sub.z. In the compound, A is at least one of an alkali metal and hydrogen, M' is a first-row transition metal, X is at least one of phosphorus, sulfur, arsenic, molybdenum, and tungsten, M'' any of a Group IIA, IIIA, IVA, VA, VIA, VIIA, VIIIA, IB, IIB, IIIB, IVB, VB, and VIB metal, D is at least one of oxygen, nitrogen, carbon, or a halogen, 0.0001storage batteries.

  1. Thermal energy storage apparatus

    SciTech Connect (OSTI)

    Thoma, P.E.

    1980-04-22

    A thermal energy storage apparatus and method employs a container formed of soda lime glass and having a smooth, defectfree inner wall. The container is filled substantially with a material that can be supercooled to a temperature greater than 5* F., such as ethylene carbonate, benzophenone, phenyl sulfoxide, di-2-pyridyl ketone, phenyl ether, diphenylmethane, ethylene trithiocarbonate, diphenyl carbonate, diphenylamine, 2benzoylpyridine, 3-benzoylpyridine, 4-benzoylpyridine, 4methylbenzophenone, 4-bromobenzophenone, phenyl salicylate, diphenylcyclopropenone, benzyl sulfoxide, 4-methoxy-4prmethylbenzophenone, n-benzoylpiperidine, 3,3pr,4,4pr,5 pentamethoxybenzophenone, 4,4'-bis-(Dimethylamino)-benzophenone, diphenylboron bromide, benzalphthalide, benzophenone oxime, azobenzene. A nucleating means such as a seed crystal, a cold finger or pointed member is movable into the supercoolable material. A heating element heats the supercoolable material above the melting temperature to store heat. The material is then allowed to cool to a supercooled temperature below the melting temperature, but above the natural, spontaneous nucleating temperature. The liquid in each container is selectively initiated into nucleation to release the heat of fusion. The heat may be transferred directly or through a heat exchange unit within the material.

  2. KERENA safety concept in the context of the Fukushima accident

    SciTech Connect (OSTI)

    Zacharias, T.; Novotny, C.; Bielor, E.

    2012-07-01

    Within the last three years AREVA NP and E.On KK finalized the basic design of KERENA which is a medium sized innovative boiling water reactor, based on the operational experience of German BWR nuclear power plants (NPPs). It is a generation III reactor design with a net electrical output of about 1250 MW. It combines active safety equipment of service-proven designs with new passive safety components, both safety classified. The passive systems utilize basic laws of physics, such as gravity and natural convection, enabling them to function without electric power. Even actuation of these systems is performed thanks to basic physic laws. The degree of diversity in component and system design, achieved by combining active and passive equipment, results in a very low core damage frequency. The Fukushima accident enhanced the world wide discussion about the safety of operating nuclear power plants. World wide stress tests for operating nuclear power plants are being performed embracing both natural and man made hazards. Beside the assessment of existing power plants, also new designs are analyzed regarding the system response to beyond design base accidents. KERENA's optimal combination of diversified cooling systems (active and passive) allows passing efficiently such tests, with a high level of confidence. This paper describes the passive safety components and the KERENA reactor behavior after a Fukushima like accident. (authors)

  3. Analysis of PWR RCS Injection Strategy During Severe Accident

    SciTech Connect (OSTI)

    Wang, S.-J. [Institute of Nuclear Energy Research, Taiwan (China); Chiang, K.-S. [Institute of Nuclear Energy Research, Taiwan (China); Chiang, S.-C. [Taiwan Power Company, Taiwan (China)

    2004-05-15

    Reactor coolant system (RCS) injection is an important strategy for severe accident management of a pressurized water reactor (PWR) system. Maanshan is a typical Westinghouse PWR nuclear power plant (NPP) with large, dry containment. The severe accident management guideline (SAMG) of Maanshan NPP is developed based on the Westinghouse Owners Group (WOG) SAMG.The purpose of this work is to analyze the RCS injection strategy of PWR system in an overheated core condition. Power is assumed recovered as the vessel water level drops to the bottom of active fuel. The Modular Accident Analysis Program version 4.0.4 (MAAP4) code is chosen as a tool for analysis. A postulated station blackout sequence for Maanshan NPP is cited as a reference case for this analysis. The hot leg creep rupture occurs during the mitigation action with immediate injection after power recovery according to WOG SAMG, which is not desired. This phenomenon is not considered while developing the WOG SAMG. Two other RCS injection methods are analyzed by using MAAP4. The RCS injection strategy is modified in the Maanshan SAMG. These results can be applied for typical PWR NPPs.

  4. Enhanced Accident Tolerant Fuels for LWRS - A Preliminary Systems Analysis

    SciTech Connect (OSTI)

    Gilles Youinou; R. Sonat Sen

    2013-09-01

    The severe accident at Fukushima Daiichi nuclear plants illustrates the need for continuous improvements through developing and implementing technologies that contribute to safe, reliable and cost-effective operation of the nuclear fleet. Development of enhanced accident tolerant fuel contributes to this effort. These fuels, in comparison with the standard zircaloy – UO2 system currently used by the LWR industry, should be designed such that they tolerate loss of active cooling in the core for a longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations, operational transients, and design-basis events. This report presents a preliminary systems analysis related to most of these concepts. The potential impacts of these innovative LWR fuels on the front-end of the fuel cycle, on the reactor operation and on the back-end of the fuel cycle are succinctly described without having the pretension of being exhaustive. Since the design of these various concepts is still a work in progress, this analysis can only be preliminary and could be updated as the designs converge on their respective final version.

  5. Level 1 Accident Investigation Report of August 17, 2004, Fatal...

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

    while stringing "sock line" to enable the subsequent stringing of new conductors and static wire on the Grand Coulee-Bell 6 500-kV line between tower 842 and BPA's Bell...

  6. An analysis of railroad accident dynamics in College Station, Texas 

    E-Print Network [OSTI]

    Brown, Hart Stefan

    1998-01-01

    The intersection between the Union Pacific Railroad (UP) Valley Junction line and Texas A&M University (TAMU) poses a significant potential or risk to the people who utilize the campus. The line carried over I 1,000 loads ...

  7. Analysis in support of storage of residues in the pipe overpack container

    SciTech Connect (OSTI)

    Ludwigsen, J.S.; Ammerman, D.J.; Radloff, H.D.

    1998-04-01

    The disposition of the large backlog of plutonium residues at the Rocky Flats Environmental Technology Site (Rocky Flats) will require interim storage and subsequent shipment to a waste repository. Current plans call for disposal at the Waste Isolation Pilot Plant (WIPP) and the transportation to WIPP in the TRUPACT-II. The transportation phase will require the residues to be packaged in a container that is more robust than a standard 55 gallon waste drum. Rocky Flats has designed the Pipe Overpack Container to meet this need. The potential for damage to this container during onsite storage in unhardened structures for several hypothetical accident scenarios has been addressed using finite element calculations. This report will describe the initial conditions and assumptions for these analyses and the predicted response of the container.

  8. Production, Storage, and FC Analysis

    Broader source: Energy.gov [DOE]

    Presentation on Production, Storage, and FC Analysis to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004 to discuss and define role of systems analysis in DOE Hydrogen Program.

  9. Efficient storage of versioned matrices

    E-Print Network [OSTI]

    Seering, Adam B

    2011-01-01

    Versioned-matrix storage is increasingly important in scientific applications. Various computer-based scientific research, from astronomy observations to weather predictions to mechanical finite-element analyses, results ...

  10. Device-transparent personal storage

    E-Print Network [OSTI]

    Strauss, Jacob A. (Jacob Alo), 1979-

    2010-01-01

    Users increasingly store data collections such as digital photographs on multiple personal devices, each of which typically presents the user with a storage management interface isolated from the contents of all other ...

  11. A Successful Cool Storage Rate 

    E-Print Network [OSTI]

    Ahrens, A. C.; Sobey, T. M.

    1994-01-01

    local natural gas distribution company. The end result is a very successful cool storage program with 52 projects and 31 megawatts of demand reduction in the first three and one-half years of program implementation....

  12. Hydrogen Storage "Think Tank" Report

    Broader source: Energy.gov [DOE]

    This report is a compilation of information exchanged at a forum on March 14, 2003 in Washington, DC. The forum was assembled for innovative and non-conventional brainstorming on this issue of hydrogen storage technologies.

  13. Compressed air energy storage system

    DOE Patents [OSTI]

    Ahrens, Frederick W. (Naperville, IL); Kartsounes, George T. (Naperville, IL)

    1981-01-01

    An internal combustion reciprocating engine is operable as a compressor during slack demand periods utilizing excess power from a power grid to charge air into an air storage reservoir and as an expander during peak demand periods to feed power into the power grid utilizing air obtained from the air storage reservoir together with combustible fuel. Preferably the internal combustion reciprocating engine is operated at high pressure and a low pressure turbine and compressor are also employed for air compression and power generation.

  14. Lih thermal energy storage device

    DOE Patents [OSTI]

    Olszewski, Mitchell (Knoxville, TN); Morris, David G. (Knoxville, TN)

    1994-01-01

    A thermal energy storage device for use in a pulsed power supply to store waste heat produced in a high-power burst operation utilizes lithium hydride as the phase change thermal energy storage material. The device includes an outer container encapsulating the lithium hydride and an inner container supporting a hydrogen sorbing sponge material such as activated carbon. The inner container is in communication with the interior of the outer container to receive hydrogen dissociated from the lithium hydride at elevated temperatures.

  15. Analysis of main steam isolation valve leakage in design basis accidents using MELCOR 1.8.6 and RADTRAD.

    SciTech Connect (OSTI)

    Salay, Michael; Kalinich, Donald A.; Gauntt, Randall O.; Radel, Tracy E.

    2008-10-01

    Analyses were performed using MELCOR and RADTRAD to investigate main steam isolation valve (MSIV) leakage behavior under design basis accident (DBA) loss-of-coolant (LOCA) conditions that are presumed to have led to a significant core melt accident. Dose to the control room, site boundary and LPZ are examined using both approaches described in current regulatory guidelines as well as analyses based on best estimate source term and system response. At issue is the current practice of using containment airborne aerosol concentrations as a surrogate for the in-vessel aerosol concentration that exists in the near vicinity of the MSIVs. This study finds current practice using the AST-based containment aerosol concentrations for assessing MSIV leakage is non-conservative and conceptually in error. A methodology is proposed that scales the containment aerosol concentration to the expected vessel concentration in order to preserve the simplified use of the AST in assessing containment performance under assumed DBA conditions. This correction is required during the first two hours of the accident while the gap and early in-vessel source terms are present. It is general practice to assume that at {approx}2hrs, recovery actions to reflood the core will have been successful and that further core damage can be avoided. The analyses performed in this study determine that, after two hours, assuming vessel reflooding has taken place, the containment aerosol concentration can then conservatively be used as the effective source to the leaking MSIV's. Recommendations are provided concerning typical aerosol removal coefficients that can be used in the RADTRAD code to predict source attenuation in the steam lines, and on robust methods of predicting MSIV leakage flows based on measured MSIV leakage performance.

  16. Nonaqueous Electrical Storage Device

    DOE Patents [OSTI]

    McEwen, Alan B. (Melrose, MA); Evans, David A. (Seekonk, MA); Blakley, Thomas J. (Woburn, MA); Goldman, Jay L. (Mansfield, MA)

    1999-10-26

    An electrochemical capacitor is disclosed that features two, separated, high surface area carbon cloth electrodes sandwiched between two current collectors fabricated of a conductive polymer having a flow temperature greater than 130.degree. C., the perimeter of the electrochemical capacitor being sealed with a high temperature gasket to form a single cell device. The gasket material is a thermoplastic stable at temperatures greater than 100.degree. C., preferably a polyester or a polyurethane, and having a reflow temperature above 130.degree. C. but below the softening temperature of the current collector material. The capacitor packaging has good mechanical integrity over a wide temperature range, contributes little to the device equivalent series resistance (ESR), and is stable at high potentials. In addition, the packaging is designed to be easily manufacturable by assembly line methods. The individual cells can be stacked in parallel or series configuration to reach the desired device voltage and capacitance.

  17. FAFCO Ice Storage test report

    SciTech Connect (OSTI)

    Stovall, T.K.

    1993-11-01

    The Ice Storage Test Facility (ISTF) is designed to test commercial ice storage systems. FAFCO provided a storage tank equipped with coils designed for use with a secondary fluid system. The FAFCO ice storage system was tested over a wide range of operating conditions. Measured system performance during charging showed the ability to freeze the tank fully, storing from 150 to 200 ton-h. However, the charging rate showed significant variations during the latter portion of the charge cycle. During discharge cycles, the storage tank outlet temperature was strongly affected by the discharge rate and tank state of charge. The discharge capacity was dependent upon both the selected discharge rate and maximum allowable tank outlet temperature. Based on these tests, storage tank selection must depend on both charge and discharge conditions. This report describes FAFCO system performance fully under both charging and discharging conditions. While the test results reported here are accurate for the prototype 1990 FAFCO Model 200, currently available FAFCO models incorporate significant design enhancements beyond the Model 200. At least one major modification was instituted as a direct result of the ISTF tests. Such design improvements were one of EPRI`s primary goals in founding the ISTF.

  18. Thermal storage module for solar dynamic receivers

    DOE Patents [OSTI]

    Beatty, Ronald L. (Farragut, TN); Lauf, Robert J. (Oak Ridge, TN)

    1991-01-01

    A thermal energy storage system comprising a germanium phase change material and a graphite container.

  19. Hydrogen Storage Technologies Roadmap, November 2005

    Fuel Cell Technologies Publication and Product Library (EERE)

    Document describing plan for research into and development of hydrogen storage technology for transportation applications.

  20. Electric Storage in California's Commercial Buildings

    E-Print Network [OSTI]

    Stadler, Michael

    2014-01-01

    microgrid can be fuel cells, PV, solar thermal, stationary storage, absorption cooling, combined heat and power,

  1. 1 Files and Databases mass storage

    E-Print Network [OSTI]

    Verschelde, Jan

    Outline 1 Files and Databases mass storage hash functions 2 Dictionaries logical key values nested Jan Verschelde, 28 January 2015 Intro to Computer Science (MCS 260) mass storage and dictionaries L-7 28 January 2015 1 / 32 #12;mass storage dictionaries in Python 1 Files and Databases mass storage

  2. Addressing the Grand Challenges in Energy Storage

    SciTech Connect (OSTI)

    Liu, Jun

    2013-02-25

    The editorial summarizes the contents of the special issue for energy storage in Advanced Functional Materials.

  3. Optimize Storage Placement in Sensor Networks

    E-Print Network [OSTI]

    Li, Qun

    of limited storage, communication capacity, and battery power is ameliorated. Placing storage nodesOptimize Storage Placement in Sensor Networks Bo Sheng, Member, IEEE, Qun Li, Member, IEEE, and Weizhen Mao Abstract--Data storage has become an important issue in sensor networks as a large amount

  4. Hydrogen Storage at Lawrence Berkeley National Laboratory

    Broader source: Energy.gov [DOE]

    Presentation from the Hydrogen Storage Pre-Solicitation Meeting held June 19, 2003 in Washington, DC.

  5. Energy Storage Management for VG Integration (Presentation)

    SciTech Connect (OSTI)

    Kirby, B.

    2011-10-01

    This presentation describes how you economically manage integration costs of storage and variable generation.

  6. New York's Energy Storage System Gets Recharged

    Broader source: Energy.gov [DOE]

    Jonathan Silver and Matt Rogers on a major breakthrough for New York state's energy storage capacity.

  7. AQUIFER STORAGE SITE EVALUATION AND MONITORING

    E-Print Network [OSTI]

    Edwards, Mike

    on the market sectors of electricity transmission, gas transmission, storage and distribution and process

  8. A Perspective on Long-Term Recovery Following the Fukushima Nuclear Accident - 12075

    SciTech Connect (OSTI)

    Chen, S.Y. [Environmental Science Division, Argonne National Laboratory, Argonne, IL (United States)

    2012-07-01

    The tragic events at the Fukushima Daiichi Nuclear Power Station began occurring on March 11, 2011, following Japan's unprecedented earthquake and tsunami. The subsequent loss of external power and on-site cooling capacity severely compromised the plant's safety systems, and subsequently, led to core melt in the affected reactors and damage to spent nuclear fuel in the storage pools. Together with hydrogen explosions, this resulted in a substantial release of radioactive material to the environment (mostly Iodine-131 and Cesium- 137), prompting an extensive evacuation effort. The latest release estimate places the event at the highest severity level (Level 7) on the International Nuclear Event Scale, the same as the Chernobyl accident of 1986. As the utility owner endeavored to stabilize the damaged facility, environmental contamination continued to propagate and affect every aspect of daily life in the affected region of Japan. Elevated levels of radioactivity (mostly dominated by Cs-137 with the passage of time) were found in soil, drinking water, vegetation, produce, seafood, and other foodstuffs. An estimated 80,000 to 90,000 people were evacuated; more evacuations are being contemplated months after the accident, and a vast amount of land has become contaminated. Early actions were taken to ban the shipment and sale of contaminated food and drinking water, followed by later actions to ban the shipment and sale of contaminated beef, mushrooms, and seafood. As the event continues to evolve toward stabilization, the long-term recovery effort needs to commence - a process that doubtless will involve rather complex decision-making interactions between various stakeholders. Key issues that may be encountered and considered in such a process include (1) socio-political factors, (2) local economic considerations, (3) land use options, (4) remediation approaches, (5) decontamination methods, (6) radioactive waste management, (7) cleanup levels and options, and (8) government policies, among others. This paper offers a perspective on this likely long and arduous journey toward establishing a 'new normal' that will ultimately take shape. Toward this end, it is important to evaluate the 'optimization' process advocated by the international community in achieving long-term recovery from this particularly fateful event in Fukushima. In the process, experience and lessons learned from past events will be fully evaluated and considered. (author)

  9. Making the case for direct hydrogen storage in fuel cell vehicles

    SciTech Connect (OSTI)

    James, B.D.; Thomas, C.E.; Baum, G.N.; Lomas, F.D. Jr.; Kuhn, I.F. Jr.

    1997-12-31

    Three obstacles to the introduction of direct hydrogen fuel cell vehicles are often states: (1) inadequate onboard hydrogen storage leading to limited vehicle range; (2) lack of an hydrogen infrastructure, and (3) cost of the entire fuel cell system. This paper will address the first point with analysis of the problem/proposed solutions for the remaining two obstacles addressed in other papers. Results of a recent study conducted by Directed Technologies Inc. will be briefly presented. The study, as part of Ford Motor Company/DOE PEM Fuel Cell Program, examines multiple pure hydrogen onboard storage systems on the basis of weight, volume, cost, and complexity. Compressed gas, liquid, carbon adsorption, and metal hydride storage are all examined with compressed hydrogen storage at 5,000 psia being judged the lowest-risk, highest benefit, near-term option. These results are combined with recent fuel cell vehicle drive cycle simulations to estimate the onboard hydrogen storage requirement for full vehicle range (380 miles on the combined Federal driving schedule). The results indicate that a PNGV-like vehicle using powertrain weights and performance realistically available by the 2004 PNGV target data can achieve approximate fuel economy equivalent to 100 mpg on gasoline (100 mpg{sub eq}) and requires storage of approximately 3.6 kg hydrogen for full vehicle storage quantity allows 5,000 psia onboard storage without altering the vehicle exterior lines or appreciably encroaching on the passenger or trunk compartments.

  10. Investigations in cool thermal storage: storage process optimization and glycol sensible storage enhancement 

    E-Print Network [OSTI]

    Abraham, Michaela Marie

    1993-01-01

    of 10'F, the irreversibility developed from the heat transfer between the tank water and the refrigerant increases with lower freezing temperatures. The second part of this study presents a simplified optimization method for a pure water, ice storage...

  11. Building Trust in Storage Outsourcing: Secure Accounting of Utility Storage Vishal Kher and Yongdae Kim

    E-Print Network [OSTI]

    Kim, Yongdae

    Building Trust in Storage Outsourcing: Secure Accounting of Utility Storage Vishal Kher and Yongdae are witnessing a revival of Storage Service Providers in the form of new vendors as well as traditional players. While storage outsourcing is cost-effective, many compa- nies are hesitating to outsource their storage

  12. Remote I/O Optimization and Evaluation for Tertiary Storage Systems through Storage Resource Broker

    E-Print Network [OSTI]

    Liao, Wei-keng

    Remote I/O Optimization and Evaluation for Tertiary Storage Systems through Storage Resource Broker storage systems emerge as a popular place to hold them. SRB, a uniform interface to various storage systems including tertiary storage systems such as HPSS, UniTree etc., becomes an important and convenient

  13. SPEK: A Storage Performance Evaluation Kernel Module for Block Level Storage Systems under

    E-Print Network [OSTI]

    Yang, Qing "Ken"

    1 SPEK: A Storage Performance Evaluation Kernel Module for Block Level Storage Systems under Faulty), for evaluating the performance of block-level storage systems in the presence of faults as well as under normal operations. SPEK can work on both Direct Attached Storage (DAS) and block level networked storage systems

  14. SPEK: A Storage Performance Evaluation Kernel Module for Block Level Storage Systems

    E-Print Network [OSTI]

    He, Xubin "Ben"

    SPEK: A Storage Performance Evaluation Kernel Module for Block Level Storage Systems Ming Zhang storage systems at block level. It can be used for both DAS (Direct Attached Storage) and block level networked storage systems. Each SPEK tool consists of a controller, several workers, and one or more probers

  15. Routing, Storage Management and Caching, and Security of Peer-to-Peer Storage Systems

    E-Print Network [OSTI]

    Zhu, Yingwu "Jason"

    Routing, Storage Management and Caching, and Security of Peer-to-Peer Storage Systems Yingwu Zhu such as Napster, Gnutella and Freenet, has inspired a whole new breed of P2P storage systems, which aims-tolerant, and highly-available storage without centralized servers. Many P2P storage systems have been proposed

  16. Key Parameters for Operator Diagnosis of BWR Plant Condition during a Severe Accident

    SciTech Connect (OSTI)

    Clayton, Dwight A.; Poore, III, Willis P.

    2015-01-01

    The objective of this research is to examine the key information needed from nuclear power plant instrumentation to guide severe accident management and mitigation for boiling water reactor (BWR) designs (specifically, a BWR/4-Mark I), estimate environmental conditions that the instrumentation will experience during a severe accident, and identify potential gaps in existing instrumentation that may require further research and development. This report notes the key parameters that instrumentation needs to measure to help operators respond to severe accidents. A follow-up report will assess severe accident environmental conditions as estimated by severe accident simulation model analysis for a specific US BWR/4-Mark I plant for those instrumentation systems considered most important for accident management purposes.

  17. Printed circuit dispersive transmission line

    DOE Patents [OSTI]

    Ikezi, H.; Lin-Liu, Y.R.; DeGrassie, J.S.

    1991-08-27

    A printed circuit dispersive transmission line structure is disclosed comprising an insulator, a ground plane formed on one surface of the insulator, a first transmission line formed on a second surface of the insulator, and a second transmission line also formed on the second surface of the insulator and of longer length than the first transmission line and periodically intersecting the first transmission line. In a preferred embodiment, the transmission line structure exhibits highly dispersive characteristics by designing the length of one of the transmission line between two adjacent periodic intersections to be longer than the other. 5 figures.

  18. Printed circuit dispersive transmission line

    DOE Patents [OSTI]

    Ikezi, Hiroyuki (Rancho Santa Fe, CA); Lin-Liu, Yuh-Ren (San Diego, CA); DeGrassie, John S. (Encinitas, CA)

    1991-01-01

    A printed circuit dispersive transmission line structure is disclosed comprising an insulator, a ground plane formed on one surface of the insulator, a first transmission line formed on a second surface of the insulator, and a second transmission line also formed on the second surface of the insulator and of longer length than the first transmission line and periodically intersecting the first transmission line. In a preferred embodiment, the transmission line structure exhibits highly dispersive characteristics by designing the length of one of the transmission line between two adjacent periodic intersections to be longer than the other.

  19. Conductive lithium storage electrode

    DOE Patents [OSTI]

    Chiang, Yet-Ming (Framingham, MA); Chung, Sung-Yoon (Seoul, KR); Bloking, Jason T. (Cambridge, MA); Andersson, Anna M. (Uppsala, SE)

    2008-03-18

    A compound comprising a composition A.sub.x(M'.sub.1-aM''.sub.a).sub.y(XD.sub.4).sub.z, A.sub.x(M'.sub.1-aM''.sub.a).sub.y(DXD.sub.4).sub.z, or A.sub.x(M'.sub.1-aM''.sub.a).sub.y(X.sub.2D.sub.7).sub.z, and have values such that x, plus y(1-a) times a formal valence or valences of M', plus ya times a formal valence or valence of M'', is equal to z times a formal valence of the XD.sub.4, X.sub.2D.sub.7, or DXD.sub.4 group; or a compound comprising a composition (A.sub.1-aM''.sub.a).sub.xM'.sub.y(XD.sub.4).sub.z, (A.sub.1-aM''.sub.a).sub.xM'.sub.y(DXD.sub.4).sub.z(A.sub.1-aM''.sub.a).s- ub.xM'.sub.y(X.sub.2D.sub.7).sub.z and have values such that (1-a).sub.x plus the quantity ax times the formal valence or valences of M'' plus y times the formal valence or valences of M' is equal to z times the formal valence of the XD.sub.4, X.sub.2D.sub.7 or DXD.sub.4 group. In the compound, A is at least one of an alkali metal and hydrogen, M' is a first-row transition metal, X is at least one of phosphorus, sulfur, arsenic, molybdenum, and tungsten, M'' any of a Group IIA, IIIA, IVA, VA, VIA, VIIA, VIIIA, IB, IIB, IIIB, IVB, VB, and VIB metal, D is at least one of oxygen, nitrogen, carbon, or a halogen, 0.0001storage batteries and can have a gravimetric capacity of at least about 80 mAh/g while being charged/discharged at greater than about C rate of the compound.

  20. Conductive lithium storage electrode

    DOE Patents [OSTI]

    Chiang, Yet-Ming (Framingham, MA); Chung, Sung-Yoon (Incheon, KR); Bloking, Jason T. (Mountain View, CA); Andersson, Anna M. (Vasteras, SE)

    2012-04-03

    A compound comprising a composition A.sub.x(M'.sub.1-aM''.sub.a).sub.y(XD.sub.4).sub.z, A.sub.x(M'.sub.1-aM''.sub.a).sub.y(DXD.sub.4).sub.z, or A.sub.x(M'.sub.1-aM''.sub.a).sub.y(X.sub.2D.sub.7).sub.z, and have values such that x, plus y(1-a) times a formal valence or valences of M', plus ya times a formal valence or valence of M'', is equal to z times a formal valence of the XD.sub.4, X.sub.2D.sub.7, or DXD.sub.4 group; or a compound comprising a composition (A.sub.1-aM''.sub.a).sub.xM'.sub.y(XD.sub.4).sub.z, (A.sub.1-aM''.sub.a).sub.xM'.sub.y(DXD.sub.4).sub.z (A.sub.1-aM''.sub.a).sub.xM'.sub.y(X.sub.2D.sub.7).sub.z and have values such that (1-a).sub.x plus the quantity ax times the formal valence or valences of M'' plus y times the formal valence or valences of M' is equal to z times the formal valence of the XD.sub.4, X.sub.2D.sub.7 or DXD.sub.4 group. In the compound, A is at least one of an alkali metal and hydrogen, M' is a first-row transition metal, X is at least one of phosphorus, sulfur, arsenic, molybdenum, and tungsten, M'' any of a Group IIA, IIIA, IVA, VA, VIA, VIIA, VIIIA, IB, IIB, IIIB, IVB, VB, and VIB metal, D is at least one of oxygen, nitrogen, carbon, or a halogen, 0.0001storage batteries and can have a gravimetric capacity of at least about 80 mAh/g while being charged/discharged at greater than about C rate of the compound.

  1. Calibrating transport lines using LOCO techniques

    SciTech Connect (OSTI)

    Yves Roblin

    2011-09-01

    With the 12GeV upgrade underway at CEBAF, there is a need to re-characterize the beamlines after the modifications made to it to accommodate running at higher energies. We present a linear perturbation approach to calibrating the optics model of transport lines. This method is adapted from the LOCO method in use for storage rings. We consider the effect of quadrupole errors, dipole construction errors as well as beam position monitors and correctors calibrations. The ideal model is expanded to first order in Taylor series of the quadrupole errors. A set of difference orbits obtained by exciting the correctors along the beamline is taken, yielding the measured response matrix. An iterative procedure is invoked and the quadrupole errors as well as beam position monitors and corrector calibration factors are obtained. Here we present details of the method and results of first measurements at CEBAF in early 2011.

  2. Improved dose assessment in a nuclear reactor accident using the old and new ICRP methodologies 

    E-Print Network [OSTI]

    Yoon, Suk-Chul

    1987-01-01

    using WASH-1400 methodologies will be presented later with discussion of the previous work. THEORY AND MODELING Atmospheric Dispersion Radionuclides leaking from the containment during a severe nuclear accident are dispersed continually... generic set of accident releases that could provide useful insights into improved safety action. A set of five groups of source terms were proposed (BI82) to encompass the full spectrum of severe accident release possibilities, these were called Siting...

  3. Human factors review for nuclear power plant severe accident sequence analysis

    SciTech Connect (OSTI)

    Krois, P.A.; Haas, P.M.

    1985-01-01

    The paper discusses work conducted to: (1) support the severe accident sequence analysis of a nuclear power plant transient based on an assessment of operator actions, and (2) develop a descriptive model of operator severe accident management. Operator actions during the transient are assessed using qualitative and quantitative methods. A function-oriented accident management model provides a structure for developing technical operator guidance on mitigating core damage preventing radiological release.

  4. Simulation of a small break loss of coolant accident conducted at the BETHSY Integral Test Facility 

    E-Print Network [OSTI]

    Bott, Charles Patrick

    1992-01-01

    systems where the interaction mechanisms themselves are complex and contain uncertainties. Early analysis of reactor accidents concentrated on severe accident scenarios in- volving large piping ruptures in the coolant system. These were seen... as the design basis accident for the systems, since, if the system could survive such a, scenario and maintain fuel cladding integrity, any smaller piping break would be a less severe ac- cident of one already evaluated. The duration of these large break loss...

  5. 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.

  6. Temperature of aircraft cargo flame exposure during accidents involving fuel spills

    SciTech Connect (OSTI)

    Mansfield, J.A.

    1993-01-01

    This report describes an evaluation of flame exposure temperatures of weapons contained in alert (parked) bombers due to accidents that involve aircraft fuel fires. The evaluation includes two types of accident, collisions into an alert aircraft by an aircraft that is on landing or take-off, and engine start accidents. Both the B-1B and B-52 alert aircraft are included in the evaluation.

  7. Grid Applications for Energy Storage Flow Cells for Energy Storage Workshop

    E-Print Network [OSTI]

    Storage #12;Competitive Electric Market Structure Power Generation Distributed Generation Grid Management Power Mkts. & Reliability Micro-Grids Power Quality Grid Reliability Competitive State Regulated FERCGrid Applications for Energy Storage Flow Cells for Energy Storage Workshop Washington DC 7

  8. A comparative analysis of accident risks in fossil, hydro, and nuclear energy chains

    SciTech Connect (OSTI)

    Burgherr, P.; Hirschberg, S.

    2008-07-01

    This study presents a comparative assessment of severe accident risks in the energy sector, based on the historical experience of fossil (coal, oil, natural gas, and LPG (Liquefied Petroleum Gas)) and hydro chains contained in the comprehensive Energy-related Severe Accident Database (ENSAD), as well as Probabilistic Safety Assessment (PSA) for the nuclear chain. Full energy chains were considered because accidents can take place at every stage of the chain. Comparative analyses for the years 1969-2000 included a total of 1870 severe ({>=} 5 fatalities) accidents, amounting to 81,258 fatalities. Although 79.1% of all accidents and 88.9% of associated fatalities occurred in less developed, non-OECD countries, industrialized OECD countries dominated insured losses (78.0%), reflecting their substantially higher insurance density and stricter safety regulations. Aggregated indicators and frequency-consequence (F-N) curves showed that energy-related accident risks in non-OECD countries are distinctly higher than in OECD countries. Hydropower in non-OECD countries and upstream stages within fossil energy chains are most accident-prone. Expected fatality rates are lowest for Western hydropower and nuclear power plants; however, the maximum credible consequences can be very large. Total economic damages due to severe accidents are substantial, but small when compared with natural disasters. Similarly, external costs associated with severe accidents are generally much smaller than monetized damages caused by air pollution.

  9. Type B Accident Investigation on the August 5, 2003, Pu-238 Multiple...

    Energy Savers [EERE]

    Board concluded that the direct cause of the accident was the release of airborne contamination from a degraded package that contained cellulose material and plutonium-238...

  10. Integrating accident management issues in the design of future reactors EDF tentative approach

    SciTech Connect (OSTI)

    Berbey, P.; Vidard, M. [EDF-SEPTEN, Villeurbanne (France)

    1997-12-01

    In next generation plants, Severe Accidents will be explicitly considered at a very early stage of the design, and risk significant challenges will be addressed as appropriate. As design provisions could be considered to address some of these challenges, the need for Severe Accident Management (SAM) could be debated. For EDF, Accident Management (AM) in general, and SAM in particular, will remain a cornerstone of plant safety. Design provisions, if any, will have to be such as not to preclude any SAM measure with the potential for preventing accident sequences from progressing further. 3 refs., 2 figs.

  11. Level 1 Accident Report of the March 1, 2010 Bobcat Fatality...

    Energy Savers [EERE]

    Bluffs Substation March 31, 2010 On March 2, 2010 at the request of the Bonneville Power Administration (BPA) Chief Safety Officer, a Level I Accident Investigation was...

  12. Order Module--DOE Order 225.1B, ACCIDENT INVESTIGATIONS

    Office of Energy Efficiency and Renewable Energy (EERE)

    DOE O 225.1B prescribes organizational responsibilities, authorities, and requirements for conducting investigations of certain accidents occurring at DOE sites, facilities, areas, operations, and...

  13. Summary of the SRS Severe Accident Analysis Program, 1987--1992

    SciTech Connect (OSTI)

    Long, T.A.; Hyder, M.L.; Britt, T.E.; Allison, D.K.; Chow, S.; Graves, R.D.; DeWald, A.B. Jr.; Monson, P.R. Jr.; Wooten, L.A.

    1992-11-01

    The Severe Accident Analysis Program (SAAP) is a program of experimental and analytical studies aimed at characterizing severe accidents that might occur in the Savannah River Site Production Reactors. The goals of the Severe Accident Analysis Program are: To develop an understanding of severe accidents in SRS reactors that is adequate to support safety documentation for these reactors, including the Safety Analysis Report (SAR), the Probabilistic Risk Assessment (PRA), and other studies evaluating the safety of reactor operation; To provide tools and bases for the evaluation of existing or proposed safety related equipment in the SRS reactors; To provide bases for the development of accident management procedures for the SRS reactors; To develop and maintain on the site a sufficient body of knowledge, including documents, computer codes, and cognizant engineers and scientists, that can be used to authoritatively resolve questions or issues related to reactor accidents. The Severe Accident Analysis Program was instituted in 1987 and has already produced a substantial amount of information, and specialized calculational tools. Products of the Severe Accident Analysis Program (listed in Section 9 of this report) have been used in the development of the Safety Analysis Report (SAR) and the Probabilistic Risk Assessment (PRA), and in the development of technical specifications for the SRS reactors. A staff of about seven people is currently involved directly in the program and in providing input on severe accidents to other SRS activities.

  14. Safety evaluation of MHTGR licensing basis accident scenarios

    SciTech Connect (OSTI)

    Kroeger, P.G.

    1989-04-01

    The safety potential of the Modular High-Temperature Gas Reactor (MHTGR) was evaluated, based on the Preliminary Safety Information Document (PSID), as submitted by the US Department of Energy to the US Nuclear Regulatory Commission. The relevant reactor safety codes were extended for this purpose and applied to this new reactor concept, searching primarily for potential accident scenarios that might lead to fuel failures due to excessive core temperatures and/or to vessel damage, due to excessive vessel temperatures. The design basis accident scenario leading to the highest vessel temperatures is the depressurized core heatup scenario without any forced cooling and with decay heat rejection to the passive Reactor Cavity Cooling System (RCCS). This scenario was evaluated, including numerous parametric variations of input parameters, like material properties and decay heat. It was found that significant safety margins exist, but that high confidence levels in the core effective thermal conductivity, the reactor vessel and RCCS thermal emissivities and the decay heat function are required to maintain this safety margin. Severe accident extensions of this depressurized core heatup scenario included the cases of complete RCCS failure, cases of massive air ingress, core heatup without scram and cases of degraded RCCS performance due to absorbing gases in the reactor cavity. Except for no-scram scenarios extending beyond 100 hr, the fuel never reached the limiting temperature of 1600/degree/C, below which measurable fuel failures are not expected. In some of the scenarios, excessive vessel and concrete temperatures could lead to investment losses but are not expected to lead to any source term beyond that from the circulating inventory. 19 refs., 56 figs., 11 tabs.

  15. Markov Model of Accident Progression at Fukushima Daiichi

    SciTech Connect (OSTI)

    Cuadra A.; Bari R.; Cheng, L-Y; Ginsberg, T.; Lehner, J.; Martinez-Guridi, G.; Mubayi, V.; Pratt, T.; Yue, M.

    2012-11-11

    On March 11, 2011, a magnitude 9.0 earthquake followed by a tsunami caused loss of offsite power and disabled the emergency diesel generators, leading to a prolonged station blackout at the Fukushima Daiichi site. After successful reactor trip for all operating reactors, the inability to remove decay heat over an extended period led to boil-off of the water inventory and fuel uncovery in Units 1-3. A significant amount of metal-water reaction occurred, as evidenced by the quantities of hydrogen generated that led to hydrogen explosions in the auxiliary buildings of the Units 1 & 3, and in the de-fuelled Unit 4. Although it was assumed that extensive fuel damage, including fuel melting, slumping, and relocation was likely to have occurred in the core of the affected reactors, the status of the fuel, vessel, and drywell was uncertain. To understand the possible evolution of the accident conditions at Fukushima Daiichi, a Markov model of the likely state of one of the reactors was constructed and executed under different assumptions regarding system performance and reliability. The Markov approach was selected for several reasons: It is a probabilistic model that provides flexibility in scenario construction and incorporates time dependence of different model states. It also readily allows for sensitivity and uncertainty analyses of different failure and repair rates of cooling systems. While the analysis was motivated by a need to gain insight on the course of events for the damaged units at Fukushima Daiichi, the work reported here provides a more general analytical basis for studying and evaluating severe accident evolution over extended periods of time. This work was performed at the request of the U.S. Department of Energy to explore 'what-if' scenarios in the immediate aftermath of the accidents.

  16. Drill string transmission line

    DOE Patents [OSTI]

    Hall, David R. (Provo, UT); Hall, Jr., H. Tracy (Provo, UT); Pixton, David S. (Lehi, UT); Bradford, Kline (Orem, UT); Fox, Joe (Spanish Fork, UT)

    2006-03-28

    A transmission line assembly for transmitting information along a downhole tool comprising a pin end, a box end, and a central bore traveling between the pin end and the box end, is disclosed in one embodiment of the invention as including a protective conduit. A transmission line is routed through the protective conduit. The protective conduit is routed through the central bore and the ends of the protective conduit are routed through channels formed in the pin end and box end of the downhole tool. The protective conduit is elastically forced into a spiral or other non-linear path along the interior surface of the central bore by compressing the protective conduit to a length within the downhole tool shorter than the protective conduit.

  17. Analysis of Three Mile Island-Unit 2 accident

    SciTech Connect (OSTI)

    Not Available

    1980-03-01

    The Nuclear Safety Analysis Center (NSAC) of the Electric Power Research Institute has analyzed the Three Mile Island-2 accident. Early results of this analysis were a brief narrative summary, issued in mid-May 1979 and an initial version of this report issued later in 1979 as noted in the Foreword. The present report is a revised version of the 1979 report, containing summaries, a highly detailed sequence of events, a comparison of that sequence of events with those from other sources, 25 appendices, references and a list of abbreviations and acronyms. A matrix of equipment and system actions is included as a folded insert.

  18. Advance plant severe accident/thermal hydraulic issues for ACRS

    SciTech Connect (OSTI)

    Kress, T.S.

    1994-09-01

    The ACRS has been reviewing various advance plant designs for certification. The most active reviews have been for the ABWR, AP600, and System 80+. We have completed the reviews for ABWR and System 80+ and are presently concentrating on AP600. The ACRS gave essentially unqualified certification approval for the two completed reviews, yet,,during the process of review a number of issues arose and the plant designs changed somewhat to accommodate some of the ACRS concerns. In this talk, I will describe some of the severe accident and thermal hydraulic related issues we discussed in our reviews.

  19. Locations of criticality alarms and nuclear accident dosimeters at Hanford

    SciTech Connect (OSTI)

    Not Available

    1992-08-01

    Hanford facilities that contain fissionable materials capable of achieving critical mass are monitored with nuclear accident dosimeters (NADS) in compliance with the requirements of DOE Order 5480.11, Chapter XI, Section 4.c. (DOE 1988). The US Department of Energy (DOE) Richland Field Office (RL) has assigned the responsibility for maintaining and evaluating the Hanford NAD system to the Instrumentation and External Dosimetry (I ED) Section of Pacific Northwest Laboratory's (PNL's) Health Physics Department. This manual provides a description of the Hanford NAD, criteria and instructions for proper NAD placement, and the locations of these dosimeters onsite.

  20. Fission product release from irradiated LWR fuel under accident conditions

    SciTech Connect (OSTI)

    Strain, R.V.; Sanecki, J.E.; Osborne, M.F.

    1984-01-01

    Fission product release from irradiated LWR fuel is being studied by heating fuel rod segments in flowing steam and an inert carrier gas to simulate accident conditions. Fuels with a range of irradiation histories are being subjected to several steam flow rates over a wide range of temperatures. Fission product release during each test is measured by gamma spectroscopy and by detailed examination of the collection apparatus after the test has been completed. These release results are complemented by a detailed posttest examination of samples of the fuel rod segment. Results of release measurements and fuel rod characterizations for tests at 1400 through 2000/sup 0/C are presented in this paper.

  1. Accident Investigation Report - Fire Report | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustments (BillionProvedTravel TravelChallenges | Department of Energy ASHRAEUs About UstheAccident

  2. In a mining accident, first responders are working against

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would likeUniverseIMPACT EVALUATION PLAN FOR THE SITE-218 58ImprovingIna mining accident, first

  3. TRACE/PARCS Core Modeling of a BWR/5 for Accident Analysis of ATWS Events

    SciTech Connect (OSTI)

    Cuadra A.; Baek J.; Cheng, L.; Aronson, A.; Diamond, D.; Yarsky, P.

    2013-11-10

    The TRACE/PARCS computational package [1, 2] isdesigned to be applicable to the analysis of light water reactor operational transients and accidents where the coupling between the neutron kinetics (PARCS) and the thermal-hydraulics and thermal-mechanics (TRACE) is important. TRACE/PARCS has been assessed for itsapplicability to anticipated transients without scram(ATWS) [3]. The challenge, addressed in this study, is to develop a sufficiently rigorous input model that would be acceptable for use in ATWS analysis. Two types of ATWS events were of interest, a turbine trip and a closure of main steam isolation valves (MSIVs). In the first type, initiated by turbine trip, the concern is that the core will become unstable and large power oscillations will occur. In the second type,initiated by MSIV closure,, the concern is the amount of energy being placed into containment and the resulting emergency depressurization. Two separate TRACE/PARCS models of a BWR/5 were developed to analyze these ATWS events at MELLLA+ (maximum extended load line limit plus)operating conditions. One model [4] was used for analysis of ATWS events leading to instability (ATWS-I);the other [5] for ATWS events leading to emergency depressurization (ATWS-ED). Both models included a large portion of the nuclear steam supply system and controls, and a detailed core model, presented henceforth.

  4. Aging and loss-of-coolant accident (LOCA) testing of electrical connections

    SciTech Connect (OSTI)

    Nelson, C.F. [Sandia National Labs., Albuquerque, NM (United States)] [Sandia National Labs., Albuquerque, NM (United States)

    1998-01-01

    This report presents the results of an experimental program to determine the aging and loss-of-coolant accident (LOCA) behavior of electrical connections in order to obtain an initial scoping of their performance. Ten types of connections commonly used in nuclear power plants were tested. These included 3 types of conduit seals, 2 types of cable-to-device connectors, 3 types of cable-to-cable connectors, and 2 types of in-line splices. The connections were aged for 6 months under simultaneous thermal (99 C) and radiation (46 Gy/hr) conditions. A simulated LOCA consisting of sequential high dose-rate irradiation (3 kGy/hr) and high-temperature steam exposures followed the aging. Connection functionality was monitored using insulation resistance measurements during the aging and LOCA exposures. Because only 5 of the 10 connection types passed a post-LOCA, submerged dielectric withstand test, further detailed investigation of electrical connections and the effects of cable jacket integrity on the cable-connection system is warranted.

  5. Hydrogen Mitigation Strategy of the APR1400 Nuclear Power Plant for a Hypothetical Station Blackout Accident

    SciTech Connect (OSTI)

    Kim, Jongtae; Hong, Seong-Wan; Kim, Sang-Baik; Kim, Hee-Dong [Korea Atomic Energy Research Institute (Korea, Republic of)

    2005-06-15

    In order to analyze the hydrogen distribution during a hypothetical station blackout accident in the Korean next-generation Advanced Power Reactor 1400 (APR1400) containment, the three-dimensional computational fluid dynamics code GASFLOW was used. The source of the hydrogen and steam for the GASFLOW analysis was obtained from a MAAP calculation. The discharged water, steam, and hydrogen from the pressurizer are released into the water of the in-containment refueling water storage tank (IRWST). Most of the discharged steam is condensed in the IRWST water because of its subcooling, and dry hydrogen is released into the free volume of the IRWST; finally, it goes out to the annular compartment above the IRWST through the vent holes. From the GASFLOW analysis, it was found that the gas mixture in the IRWST becomes quickly nonflammable by oxygen starvation but the hydrogen is accumulated in the annular compartment because of the narrow ventilation gap between the operating deck and containment wall when the igniters installed in the IRWST are not operated. When the igniters installed in the APR1400 were turned on, a short period of burning occurred in the IRWST, and then the flame was extinguished by the oxygen starvation in the IRWST. The unburned hydrogen was released into the annular compartment and went up to the dome because no igniters are installed around the annular compartment in the base design of the APR1400. From this result, it could be concluded that the control of the hydrogen concentration is difficult for the base design. In this study design modifications are proposed and evaluated with GASFLOW in view of the hydrogen mitigation strategy.

  6. Assessment of the potential for ferrocyanide propagating reaction accidents

    SciTech Connect (OSTI)

    Meacham, J.E., Westinghouse Hanford

    1996-07-03

    The risk posed by the continued storage of ferrocyanide wastes in Hanford Site underground storage tanks has been studied extensively using theoretical analyses, laboratory experiments,tank monitoring, and waste sampling. This report provides an assessment of this hazard and provides the technical basis to resolve the Ferrocyanide Safety Issue for the 18 tanks, and supports the removal of these tanks from the Watch List. Based on the assessment provided in this report, the ferrocyanide waste in all 18 of the current ferrocyanide Watch List tanks, is categorized as safe and cannot burn or explode.

  7. CONTINUOUS EXTRACTED BEAM IN THE AGS FAST EXTERNAL BEAM LINE.

    SciTech Connect (OSTI)

    GLENN,J.W.; TSOUPAS,N.; BROWN,K.A.; BIRYUKOV,V.M.

    2001-06-18

    A method to split off a few percent of the 6 x 10{sup 13} AGS beam delivered to the Slow External Beam (SEB) lines and send it down the Fast External Beam line (FEB) has been developed. The mission is to feed a counter experiment off the FEB that directly measures the neutrino mass using the muon storage ring. The use of normal thin septum splitters would have an excessive loss overhead and been optically difficult. The AGS Slow Extraction uses a third integer resonance with sextuple strength so the resonance width is a few percent of the beam width. This results in a low density tail which will be clipped by a bent crystal and deflected into the FEB channel. This clipping off of the tail should reduce losses in the SEB transport line. Details of modeled orbits, particle distribution and extraction trajectories into and out off the crystal will be given.

  8. Model-Predictive Cascade Mitigation in Electric Power Systems With Storage and Renewables-Part I: Theory and Implementation

    SciTech Connect (OSTI)

    Almassalkhi, MR; Hiskens, IA

    2015-01-01

    A novel model predictive control (MPC) scheme is developed for mitigating the effects of severe line-overload disturbances in electrical power systems. A piece-wise linear convex approximation of line losses is employed to model the effect of transmission line power flow on conductor temperatures. Control is achieved through a receding-horizon model predictive control (MPC) strategy which alleviates line temperature overloads and thereby prevents the propagation of outages. The MPC strategy adjusts line flows by rescheduling generation, energy storage and controllable load, while taking into account ramp-rate limits and network limitations. In Part II of this paper, the MPC strategy is illustrated through simulation of the IEEE RTS-96 network, augmented to incorporate energy storage and renewable generation.

  9. Thermal Storage Options for HVAC Systems 

    E-Print Network [OSTI]

    Weston, R. F.; Gidwani, B. N.

    1986-01-01

    is based on the specific heat of water rather than the latent 'heat of fusion of ice as in ice storage, it requires about 4 times the storage capacity of an equivalent ice storage system. ? Salt Storage: This system utilizes eutectic salts which... freeze and melt around 47 o F. Exist ing chillers can be easily retrofitted for salt storage or chilled water storage. For ice stor age systems, a direct refrigerant system or glycol chillers are suitable. This paper discusses the details of each...

  10. Carbon Capture and Storage, 2008

    SciTech Connect (OSTI)

    2009-03-19

    The U.S. Department of Energy is researching the safe implementation of a technology called carbon sequestration, also known as carbon capture and storage, or CCS. Based on an oilfield practice, this approach stores carbon dioxide, or CO2 generated from human activities for millennia as a means to mitigate global climate change. In 2003, the Department of Energys National Energy Technology Laboratory formed seven Regional Carbon Sequestration Partnerships to assess geologic formations suitable for storage and to determine the best approaches to implement carbon sequestration in each region. This video describes the work of these partnerships.

  11. Image Storage in Hot Vapors

    E-Print Network [OSTI]

    L. Zhao; T. Wang; Y. Xiao; S. F. Yelin

    2007-10-22

    We theoretically investigate image propagation and storage in hot atomic vapor. A $4f$ system is adopted for imaging and an atomic vapor cell is placed over the transform plane. The Fraunhofer diffraction pattern of an object in the object plane can thus be transformed into atomic Raman coherence according to the idea of ``light storage''. We investigate how the stored diffraction pattern evolves under diffusion. Our result indicates, under appropriate conditions, that an image can be reconstructed with high fidelity. The main reason for this procedure to work is the fact that diffusion of opposite-phase components of the diffraction pattern interfere destructively.

  12. Carbon Capture and Storage, 2008

    ScienceCinema (OSTI)

    None

    2010-01-08

    The U.S. Department of Energy is researching the safe implementation of a technology called carbon sequestration, also known as carbon capture and storage, or CCS. Based on an oilfield practice, this approach stores carbon dioxide, or CO2 generated from human activities for millennia as a means to mitigate global climate change. In 2003, the Department of Energys National Energy Technology Laboratory formed seven Regional Carbon Sequestration Partnerships to assess geologic formations suitable for storage and to determine the best approaches to implement carbon sequestration in each region. This video describes the work of these partnerships.

  13. Catalyzed borohydrides for hydrogen storage

    DOE Patents [OSTI]

    Au, Ming (Augusta, GA)

    2012-02-28

    A hydrogen storage material and process is provided in which alkali borohydride materials are created which contain effective amounts of catalyst(s) which include transition metal oxides, halides, and chlorides of titanium, zirconium, tin, and combinations of the various catalysts. When the catalysts are added to an alkali borodydride such as a lithium borohydride, the initial hydrogen release point of the resulting mixture is substantially lowered. Additionally, the hydrogen storage material may be rehydrided with weight percent values of hydrogen at least about 9 percent.

  14. Prestressed elastomer for energy storage

    DOE Patents [OSTI]

    Hoppie, Lyle O. (Birmingham, MI); Speranza, Donald (Canton, MI)

    1982-01-01

    Disclosed is a regenerative braking device for an automotive vehicle. The device includes a power isolating assembly (14), an infinitely variable transmission (20) interconnecting an input shaft (16) with an output shaft (18), and an energy storage assembly (22). The storage assembly includes a plurality of elastomeric rods (44, 46) mounted for rotation and connected in series between the input and output shafts. The elastomeric rods are prestressed along their rotational or longitudinal axes to inhibit buckling of the rods due to torsional stressing of the rods in response to relative rotation of the input and output shafts.

  15. Storage Ring | Advanced Photon Source

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust,Field-effect Photovoltaics -7541C.3X-rays3 Prepared by:'!TransportStorage RingStorage

  16. Virtual Center of Excellence for Hydrogen Storage - Chemical...

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

    Virtual Center of Excellence for Hydrogen Storage - Chemical Hydrides Virtual Center of Excellence for Hydrogen Storage - Chemical Hydrides Presentation from the Hydrogen Storage...

  17. Recommended Best Practices for the Characterization of Storage...

    Energy Savers [EERE]

    Recommended Best Practices for the Characterization of Storage Properties of Hydrogen Storage Materials - Section 6 Thermal Properties of Hydrogen Storage Materials Recommended...

  18. US DRIVE Electrochemical Energy Storage Technical Team Roadmap...

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

    Electrochemical Energy Storage Technical Team Roadmap US DRIVE Electrochemical Energy Storage Technical Team Roadmap This U.S. DRIVE electrochemical energy storage roadmap...

  19. Thermal Energy Storage for Cooling of Commercial Buildings

    E-Print Network [OSTI]

    Akbari, H.

    2010-01-01

    of Commercial Building Thermal Energy _Storage in ASEANGas Electric Company, "Thermal Energy Storage for Cooling,"LBL--25393 DE91 ,THERMAL ENERGY STORAGE FOR COOLING OF

  20. Automatic Learning of Block Storage Access Time Models

    E-Print Network [OSTI]

    Crume, Adam

    2015-01-01

    3 Storage devices 3.1 Scope ofedge-on . . . . . . . . Queueing in a storage device with noAUTOMATIC LEARNING OF BLOCK STORAGE ACCESS TIME MODELS A