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Sample records for integration facility cdif

  1. Projects at the component development and integration facility. Quarterly technical progress report, April 1, 1994--June 30, 1994

    International Nuclear Information System (INIS)

    1994-01-01

    This quarterly technical progress report presents progress on the projects at the Component Development and Integration Facility (CDIF) during the third quarter of FY94. The CDIF is a major Department of Energy test facility in Butte, Montana, operated by MSE, Inc. Projects in progress include: Biomass Remediation Project; Heavy Metal-Contaminated Soil Project; MHD Shutdown; Mine Waste Technology Pilot Program; Plasma Projects; Resource Recovery Project; and Spray Casting Project

  2. Environmental Survey preliminary report, Idaho National Engineering Laboratory, Idaho Falls, Idaho and Component Development and Integration Facility, Butte, Montana

    International Nuclear Information System (INIS)

    1988-09-01

    This report presents the preliminary findings of the first phase of the Environmental Survey of the United States Department of Energy's (DOE) Idaho National Engineering Laboratory (INEL) and Component Development and Integration Facility (CDIF), conducted September 14 through October 2, 1987. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. The team includes outside experts supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the INEL and CDIF. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations' carried on at the INEL and the CDIF, and interviews with site personnel. The Survey team developed a Sampling and Analysis (S ampersand A) Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The S ampersand A Plan will be executed by the Oak Ridge National Laboratory. When completed, the S ampersand A results will be incorporated into the INEL/CDIF Survey findings for inclusion into the Environmental Survey Summary Report. 90 refs., 95 figs., 77 tabs

  3. Environmental Survey preliminary report, Idaho National Engineering Laboratory, Idaho Falls, Idaho and Component Development and Integration Facility, Butte, Montana

    Energy Technology Data Exchange (ETDEWEB)

    1988-09-01

    This report presents the preliminary findings of the first phase of the Environmental Survey of the United States Department of Energy's (DOE) Idaho National Engineering Laboratory (INEL) and Component Development and Integration Facility (CDIF), conducted September 14 through October 2, 1987. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. The team includes outside experts supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the INEL and CDIF. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations' carried on at the INEL and the CDIF, and interviews with site personnel. The Survey team developed a Sampling and Analysis (S A) Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The S A Plan will be executed by the Oak Ridge National Laboratory. When completed, the S A results will be incorporated into the INEL/CDIF Survey findings for inclusion into the Environmental Survey Summary Report. 90 refs., 95 figs., 77 tabs.

  4. Integrated Disposal Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Located near the center of the 586-square-mile Hanford Site is the Integrated Disposal Facility, also known as the IDF.This facility is a landfill similar in concept...

  5. Coal-fired MHD test progress at the Component Development and Integration Facility

    International Nuclear Information System (INIS)

    Hart, A.T.; Rivers, T.J.; Alsberg, C.M.; Filius, K.D.

    1992-01-01

    The Component Development and Integration Facility (CDIF) is a Department of Energy test facility operated by MSE, Inc. In the fall of 1984, a 50-MW t , pressurized, slag rejecting coal-fired combustor (CFC) replaced the oil-fired combustor in the test train. In the spring of 1989, a coal-fired precombustor was added to the test hardware, and current controls were installed in the spring of 1990. In the fall of 1990, the slag rejector was installed. MSE test hardware activities included installing the final workhorse channel and modifying the coalfired combustor by installing improved design and proof-of-concept (POC) test pieces. This paper discusses the involvement of this hardware in test progress during the past year. Testing during the last year emphasized the final workhorse hardware testing. This testing will be discussed. Facility modifications and system upgrades for improved operation and duration testing will be discussed. In addition, this paper will address long-term testing plans

  6. Energy Systems Integration Facility Videos | Energy Systems Integration

    Science.gov (United States)

    Facility | NREL Energy Systems Integration Facility Videos Energy Systems Integration Facility Integration Facility NREL + SolarCity: Maximizing Solar Power on Electrical Grids Redefining What's Possible for Renewable Energy: Grid Integration Robot-Powered Reliability Testing at NREL's ESIF Microgrid

  7. Integrated Facilities and Infrastructure Plan.

    Energy Technology Data Exchange (ETDEWEB)

    Reisz Westlund, Jennifer Jill

    2017-03-01

    Our facilities and infrastructure are a key element of our capability-based science and engineering foundation. The focus of the Integrated Facilities and Infrastructure Plan is the development and implementation of a comprehensive plan to sustain the capabilities necessary to meet national research, design, and fabrication needs for Sandia National Laboratories’ (Sandia’s) comprehensive national security missions both now and into the future. A number of Sandia’s facilities have reached the end of their useful lives and many others are not suitable for today’s mission needs. Due to the continued aging and surge in utilization of Sandia’s facilities, deferred maintenance has continued to increase. As part of our planning focus, Sandia is committed to halting the growth of deferred maintenance across its sites through demolition, replacement, and dedicated funding to reduce the backlog of maintenance needs. Sandia will become more agile in adapting existing space and changing how space is utilized in response to the changing requirements. This Integrated Facilities & Infrastructure (F&I) Plan supports the Sandia Strategic Plan’s strategic objectives, specifically Strategic Objective 2: Strengthen our Laboratories’ foundation to maximize mission impact, and Strategic Objective 3: Advance an exceptional work environment that enables and inspires our people in service to our nation. The Integrated F&I Plan is developed through a planning process model to understand the F&I needs, analyze solution options, plan the actions and funding, and then execute projects.

  8. The Integral Test Facility Karlstein

    Directory of Open Access Journals (Sweden)

    Stephan Leyer

    2012-01-01

    Full Text Available The Integral Test Facility Karlstein (INKA test facility was designed and erected to test the performance of the passive safety systems of KERENA, the new AREVA Boiling Water Reactor design. The experimental program included single component/system tests of the Emergency Condenser, the Containment Cooling Condenser and the Passive Core Flooding System. Integral system tests, including also the Passive Pressure Pulse Transmitter, will be performed to simulate transients and Loss of Coolant Accident scenarios at the test facility. The INKA test facility represents the KERENA Containment with a volume scaling of 1 : 24. Component heights and levels are in full scale. The reactor pressure vessel is simulated by the accumulator vessel of the large valve test facility of Karlstein—a vessel with a design pressure of 11 MPa and a storage capacity of 125 m3. The vessel is fed by a benson boiler with a maximum power supply of 22 MW. The INKA multi compartment pressure suppression Containment meets the requirements of modern and existing BWR designs. As a result of the large power supply at the facility, INKA is capable of simulating various accident scenarios, including a full train of passive systems, starting with the initiating event—for example pipe rupture.

  9. DKIST facility management system integration

    Science.gov (United States)

    White, Charles R.; Phelps, LeEllen

    2016-07-01

    The Daniel K. Inouye Solar Telescope (DKIST) Observatory is under construction at Haleakalā, Maui, Hawai'i. When complete, the DKIST will be the largest solar telescope in the world. The Facility Management System (FMS) is a subsystem of the high-level Facility Control System (FCS) and directly controls the Facility Thermal System (FTS). The FMS receives operational mode information from the FCS while making process data available to the FCS and includes hardware and software to integrate and control all aspects of the FTS including the Carousel Cooling System, the Telescope Chamber Environmental Control Systems, and the Temperature Monitoring System. In addition it will integrate the Power Energy Management System and several service systems such as heating, ventilation, and air conditioning (HVAC), the Domestic Water Distribution System, and the Vacuum System. All of these subsystems must operate in coordination to provide the best possible observing conditions and overall building management. Further, the FMS must actively react to varying weather conditions and observational requirements. The physical impact of the facility must not interfere with neighboring installations while operating in a very environmentally and culturally sensitive area. The FMS system will be comprised of five Programmable Automation Controllers (PACs). We present a pre-build overview of the functional plan to integrate all of the FMS subsystems.

  10. Energy Systems Integration Facility News | Energy Systems Integration

    Science.gov (United States)

    Facility | NREL Energy Systems Integration Facility News Energy Systems Integration Facility Energy Dataset A massive amount of wind data was recently made accessible online, greatly expanding the Energy's National Renewable Energy Laboratory (NREL) has completed technology validation testing for Go

  11. Power Systems Integration Laboratory | Energy Systems Integration Facility

    Science.gov (United States)

    | NREL Power Systems Integration Laboratory Power Systems Integration Laboratory Research in the Energy System Integration Facility's Power Systems Integration Laboratory focuses on the microgrid applications. Photo of engineers testing an inverter in the Power Systems Integration Laboratory

  12. Design Integration of Facilities Management

    DEFF Research Database (Denmark)

    Jensen, Per Anker

    2009-01-01

    One of the problems in the building industry is a limited degree of learning from experiences of use and operation of existing buildings. Development of professional facilities management (FM) can be seen as the missing link to bridge the gap between building operation and building design....... Strategies, methods and barriers for the transfer and integration of operational knowledge into the design process are discussed. Multiple strategies are needed to improve the integration of FM in design. Building clients must take on a leading role in defining and setting up requirements and procedures...... on literature studies and case studies from the Nordic countries in Europe, including research reflections on experiences from a main case study, where the author, before becoming a university researcher, was engaged in the client organization as deputy project director with responsibility for the integration...

  13. Energy Systems Integration News | Energy Systems Integration Facility |

    Science.gov (United States)

    the Energy Systems Integration Facility as part of NREL's work with SolarCity and the Hawaiian Electric Companies. Photo by Amy Glickson, NREL Welcome to Energy Systems Integration News, NREL's monthly date on the latest energy systems integration (ESI) developments at NREL and worldwide. Have an item

  14. INTEGRITY -- Integrated Human Exploration Mission Simulation Facility

    Science.gov (United States)

    Henninger, D.; Tri, T.; Daues, K.

    It is proposed to develop a high -fidelity ground facil ity to carry out long-duration human exploration mission simulations. These would not be merely computer simulations - they would in fact comprise a series of actual missions that just happen to stay on earth. These missions would include all elements of an actual mission, using actual technologies that would be used for the real mission. These missions would also include such elements as extravehicular activities, robotic systems, telepresence and teleoperation, surface drilling technology--all using a simulated planetary landscape. A sequence of missions would be defined that get progressively longer and more robust, perhaps a series of five or six missions over a span of 10 to 15 years ranging in durat ion from 180 days up to 1000 days. This high-fidelity ground facility would operate hand-in-hand with a host of other terrestrial analog sites such as the Antarctic, Haughton Crater, and the Arizona desert. Of course, all of these analog mission simulations will be conducted here on earth in 1-g, and NASA will still need the Shuttle and ISS to carry out all the microgravity and hypogravity science experiments and technology validations. The proposed missions would have sufficient definition such that definitive requirements could be derived from them to serve as direction for all the program elements of the mission. Additionally, specific milestones would be established for the "launch" date of each mission so that R&D programs would have both good requirements and solid milestones from which to build their implementation plans. Mission aspects that could not be directly incorporated into the ground facility would be simulated via software. New management techniques would be developed for evaluation in this ground test facility program. These new techniques would have embedded metrics which would allow them to be continuously evaluated and adjusted so that by the time the sequence of missions is completed

  15. Integrated engineering system for nuclear facilities building

    International Nuclear Information System (INIS)

    Tomura, H.; Miyamoto, A.; Futami, F.; Yasuda, S.; Ohtomo, T.

    1995-01-01

    In the construction of buildings for nuclear facilities in Japan, construction companies are generally in charge of the building engineering work, coordinating with plant engineering. An integrated system for buildings (PROMOTE: PROductive MOdeling system for Total nuclear Engineering) described here is a building engineering system including the entire life cycle of buildings for nuclear facilities. A Three-dimensional (3D) building model (PRO-model) is to be in the core of the system (PROMOTE). Data sharing in the PROMOTE is also done with plant engineering systems. By providing these basic technical foundations, PROMOTE is oriented toward offering rational, highquality engineering for the projects. The aim of the system is to provide a technical foundation in building engineering. This paper discusses the characteristics of buildings for nuclear facilities and the outline of the PROMOTE. (author)

  16. Development of an integrated assay facility

    International Nuclear Information System (INIS)

    Molesworth, T.V.; Bailey, M.; Findlay, D.J.S.; Parsons, T.V.; Sene, M.R.; Swinhoe, M.T.

    1990-01-01

    The I.R.I.S. concept proposed the use of passive examination and active interrogation techniques in an integrated assay facility. A linac would generate the interrogating gamma and neutron beams. Insufficiently detailed knowledge about active neutron and gamma interrogation of 500 litre drums of cement immobilised intermediate level waste led to a research programme which is now in its main experimental stage. Measurements of interrogation responses are being made using simulated waste drums containing actinide samples and calibration sources, in an experimental assay assembly. Results show that responses are generally consistent with theory, but that improvements are needed in some areas. A preliminary appraisal of the engineering and economic aspects of integrated assay shows that correct operational sequencing is required to achieve the short cycle time needed for high throughput. The main engineering features of a facility have been identified

  17. Integrated safeguards and facility design and operations

    International Nuclear Information System (INIS)

    Tape, J.W.; Coulter, C.A.; Markin, J.T.; Thomas, K.E.

    1987-01-01

    The integration of safeguards functions to deter or detect unauthorized actions by an insider requires the careful communication and management of safeguards-relevant information on a timely basis. The traditional separation of safeguards functions into physical protection, materials control, and materials accounting often inhibits important information flows. Redefining the major safeguards functions as authorization, enforcement, and verification, and careful attention to management of information from acquisition to organization, to analysis, to decision making can result in effective safeguards integration. The careful inclusion of these ideas in facility designs and operations will lead to cost-effective safeguards systems. The safeguards authorization function defines, for example, personnel access requirements, processing activities, and materials movements/locations that are permitted to accomplish the mission of the facility. Minimizing the number of authorized personnel, limiting the processing flexibility, and maintaining up-to-date flow sheets will facilitate the detection of unauthorized activities. Enforcement of the authorized activities can be achieved in part through the use of barriers, access control systems, process sensors, and health and safety information. Consideration of safeguards requirements during facility design can improve the enforcement function. Verification includes the familiar materials accounting activities as well as auditing and testing of the other functions

  18. Integrated facilities modeling using QUEST and IGRIP

    International Nuclear Information System (INIS)

    Davis, K.R.; Haan, E.R.

    1995-01-01

    A QUEST model and associated detailed IGRIP models were developed and used to simulate several workcells in a proposed Plutonium Storage Facility (PSF). The models are being used by team members assigned to the program to improve communication and to assist in evaluating concepts and in performing trade-off studies which will result in recommendations and a final design. The model was designed so that it could be changed easily. The added flexibility techniques used to make changes easily are described in this paper in addition to techniques for integrating the QUEST and IGRIP products. Many of these techniques are generic in nature and can be applied to any modeling endeavor

  19. Carbon dioxide neutral, integrated biofuel facility

    Energy Technology Data Exchange (ETDEWEB)

    Powell, E.E.; Hill, G.A. [Department of Chemical Engineering, University of Saskatchewan, 57 Campus Drive, Saskatoon, Saskatchewan, S7N 5A9 (Canada)

    2010-12-15

    Algae are efficient biocatalysts for both capture and conversion of carbon dioxide in the environment. In earlier work, we have optimized the ability of Chlorella vulgaris to rapidly capture CO{sub 2} from man-made emission sources by varying environmental growth conditions and bioreactor design. Here we demonstrate that a coupled biodiesel-bioethanol facility, using yeast to produce ethanol and photosynthetic algae to produce biodiesel, can result in an integrated, economical, large-scale process for biofuel production. Each bioreactor acts as an electrode for a coupled complete microbial fuel cell system; the integrated cultures produce electricity that is consumed as an energy source within the process. Finally, both the produced yeast and spent algae biomass can be used as added value byproducts in the feed or food industries. Using cost and revenue estimations, an IRR of up to 25% is calculated using a 5 year project lifespan. (author)

  20. Vitrification Facility integrated system performance testing report

    International Nuclear Information System (INIS)

    Elliott, D.

    1997-01-01

    This report provides a summary of component and system performance testing associated with the Vitrification Facility (VF) following construction turnover. The VF at the West Valley Demonstration Project (WVDP) was designed to convert stored radioactive waste into a stable glass form for eventual disposal in a federal repository. Following an initial Functional and Checkout Testing of Systems (FACTS) Program and subsequent conversion of test stand equipment into the final VF, a testing program was executed to demonstrate successful performance of the components, subsystems, and systems that make up the vitrification process. Systems were started up and brought on line as construction was completed, until integrated system operation could be demonstrated to produce borosilicate glass using nonradioactive waste simulant. Integrated system testing and operation culminated with a successful Operational Readiness Review (ORR) and Department of Energy (DOE) approval to initiate vitrification of high-level waste (HLW) on June 19, 1996. Performance and integrated operational test runs conducted during the test program provided a means for critical examination, observation, and evaluation of the vitrification system. Test data taken for each Test Instruction Procedure (TIP) was used to evaluate component performance against system design and acceptance criteria, while test observations were used to correct, modify, or improve system operation. This process was critical in establishing operating conditions for the entire vitrification process

  1. Why Integrate Educational and Community Facilities?

    Science.gov (United States)

    Fessas-Emmanouil, Helen D.

    1978-01-01

    Discusses coordination of educational and community facilities in order to encourage more rational investments and more efficient use of premises. Such coordination may reduce the economic burden imposed upon citizens for the provision of separate facilities for school and community. However, implementation of such a facility presupposes radical…

  2. Geology of the Integrated Disposal Facility Trench

    International Nuclear Information System (INIS)

    Reidel, Steve P.; Fecht, Karl R.

    2005-01-01

    This report describes the geology of the integrated Disposal Facility (IDF) Trench. The stratigraphy consists of some of the youngest sediments of the Missoula floods (younger than 770 ka). The lithology is dominated sands with minor silts and gravels that are largely unconsolidated. The stratigraphy can be subdivided into five geologic units that can be mapped throughout the trench. Four of the units were deposited by the Missoula floods and the youngest consists of windblown sand and silt. The sediment has little moisture and is consistent with that observed in the characterization boreholes. The sedimentary layers are flat lying and there are no faults or folds present. Two clastic dikes were encountered, one along the west wall and one that can be traced from the north to the southwall. The north-south clastic dike nearly bifurcates the trench but the west wall clastic dike can not be traced very far east into the trench. The classic dikes consist mainly of sand with clay-lined walls. The sediment in the dikes is compacted to partly cemented and are more resistant than the layered sediments

  3. Thermal Distribution System | Energy Systems Integration Facility | NREL

    Science.gov (United States)

    Thermal Distribution System Thermal Distribution System The Energy Systems Integration Facility's . Photo of the roof of the Energy Systems Integration Facility. The thermal distribution bus allows low as 10% of its full load level). The 60-ton chiller cools water with continuous thermal control

  4. Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

    International Nuclear Information System (INIS)

    1985-09-01

    The Basis for Design established the functional requirements and design criteria for an Integral Monitored Retrievable Storage (MRS) facility. The MRS Facility design, described in this report, is based on those requirements and includes all infrastructure, facilities, and equipment required to routinely receive, unload, prepare for storage, and store spent fuel (SF), high-level waste (HLW), and transuranic waste (TRU), and to decontaminate and return shipping casks received by both rail and truck. The facility is complete with all supporting facilities to make the MRS Facility a self-sufficient installation

  5. Energy Systems Integration Laboratory | Energy Systems Integration Facility

    Science.gov (United States)

    | NREL Integration Laboratory Energy Systems Integration Laboratory Research in the Energy Systems Integration Laboratory is advancing engineering knowledge and market deployment of hydrogen technologies. Applications include microgrids, energy storage for renewables integration, and home- and station

  6. INTEGRATION OF FACILITY MODELING CAPABILITIES FOR NUCLEAR NONPROLIFERATION ANALYSIS

    Energy Technology Data Exchange (ETDEWEB)

    Gorensek, M.; Hamm, L.; Garcia, H.; Burr, T.; Coles, G.; Edmunds, T.; Garrett, A.; Krebs, J.; Kress, R.; Lamberti, V.; Schoenwald, D.; Tzanos, C.; Ward, R.

    2011-07-18

    Developing automated methods for data collection and analysis that can facilitate nuclear nonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facility modeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facility modeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facility modeling capabilities and illustrates how they could be integrated and utilized for nonproliferation analysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facility modeling tools. After considering a representative sampling of key facility modeling capabilities, the proposed integration framework is illustrated with several examples.

  7. Integration of facility modeling capabilities for nuclear nonproliferation analysis

    International Nuclear Information System (INIS)

    Garcia, Humberto; Burr, Tom; Coles, Garill A.; Edmunds, Thomas A.; Garrett, Alfred; Gorensek, Maximilian; Hamm, Luther; Krebs, John; Kress, Reid L.; Lamberti, Vincent; Schoenwald, David; Tzanos, Constantine P.; Ward, Richard C.

    2012-01-01

    Developing automated methods for data collection and analysis that can facilitate nuclear nonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facility modeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facility modeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facility modeling capabilities and illustrates how they could be integrated and utilized for nonproliferation analysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facility modeling tools. After considering a representative sampling of key facility modeling capabilities, the proposed integration framework is illustrated with several examples.

  8. Integration Of Facility Modeling Capabilities For Nuclear Nonproliferation Analysis

    International Nuclear Information System (INIS)

    Gorensek, M.; Hamm, L.; Garcia, H.; Burr, T.; Coles, G.; Edmunds, T.; Garrett, A.; Krebs, J.; Kress, R.; Lamberti, V.; Schoenwald, D.; Tzanos, C.; Ward, R.

    2011-01-01

    Developing automated methods for data collection and analysis that can facilitate nuclear nonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facility modeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facility modeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facility modeling capabilities and illustrates how they could be integrated and utilized for nonproliferation analysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facility modeling tools. After considering a representative sampling of key facility modeling capabilities, the proposed integration framework is illustrated with several examples.

  9. Integrated Facilities Management and Fixed Asset Accounting.

    Science.gov (United States)

    Golz, W. C., Jr.

    1984-01-01

    A record of a school district's assets--land, buildings, machinery, and equipment--can be a useful management tool that meets accounting requirements and provides appropriate information for budgeting, forecasting, and facilities management. (MLF)

  10. What Is Energy Systems Integration? | Energy Systems Integration Facility |

    Science.gov (United States)

    NREL What Is Energy Systems Integration? What Is Energy Systems Integration? Energy systems integration (ESI) is an approach to solving big energy challenges that explores ways for energy systems to Research Community NREL is a founding member of the International Institute for Energy Systems Integration

  11. Vehicle-to-Grid Integration | Energy Systems Integration Facility | NREL

    Science.gov (United States)

    Vehicle-to-Grid Integration Vehicle-to-Grid Integration NREL's research stands at the forefront of vehicle charging station Our work focuses on building the infrastructure and integration needed for benefit each other. Electric Vehicles NREL's research on electric vehicle (EV) grid integration examines

  12. Grid Integration Webinars | Energy Systems Integration Facility | NREL

    Science.gov (United States)

    Grid Integration Webinars Grid Integration Webinars Watch presentations from NREL analysts on various topics related to grid integration. Wind Curtailment and the Value of Transmission under a 2050 renewable curtailment under these high wind scenarios. Text Version Grid Integration Webinar: Exploring

  13. Analysis on working pressure selection of ACME integral test facility

    International Nuclear Information System (INIS)

    Chen Lian; Chang Huajian; Li Yuquan; Ye Zishen; Qin Benke

    2011-01-01

    An integral effects test facility, advanced core cooling mechanism experiment facility (ACME) was designed to verify the performance of the passive safety system and validate its safety analysis codes of a pressurized water reactor power plant. Three test facilities for AP1000 design were introduced and review was given. The problems resulted from the different working pressures of its test facilities were analyzed. Then a detailed description was presented on the working pressure selection of ACME facility as well as its characteristics. And the approach of establishing desired testing initial condition was discussed. The selected 9.3 MPa working pressure covered almost all important passive safety system enables the ACME to simulate the LOCAs with the same pressure and property similitude as the prototype. It's expected that the ACME design would be an advanced core cooling integral test facility design. (authors)

  14. Integration of Biosafety into Core Facility Management

    Science.gov (United States)

    Fontes, Benjamin

    2013-01-01

    This presentation will discuss the implementation of biosafety policies for small, medium and large core laboratories with primary shared objectives of ensuring the control of biohazards to protect core facility operators and assure conformity with applicable state and federal policies, standards and guidelines. Of paramount importance is the educational process to inform core laboratories of biosafety principles and policies and to illustrate the technology and process pathways of the core laboratory for biosafety professionals. Elevating awareness of biohazards and the biosafety regulatory landscape among core facility operators is essential for the establishment of a framework for both project and material risk assessment. The goal of the biohazard risk assessment process is to identify the biohazard risk management parameters to conduct the procedure safely and in compliance with applicable regulations. An evaluation of the containment, protective equipment and work practices for the procedure for the level of risk identified is facilitated by the establishment of a core facility registration form for work with biohazards and other biological materials with potential risk. The final step in the biocontainment process is the assumption of Principal Investigator role with full responsibility for the structure of the site-specific biosafety program plan by core facility leadership. The presentation will provide example biohazard protocol reviews and accompanying containment measures for core laboratories at Yale University.

  15. Integration of Biosafety into Core Facility Management

    OpenAIRE

    Fontes, Benjamin

    2013-01-01

    This presentation will discuss the implementation of biosafety policies for small, medium and large core laboratories with primary shared objectives of ensuring the control of biohazards to protect core facility operators and assure conformity with applicable state and federal policies, standards and guidelines. Of paramount importance is the educational process to inform core laboratories of biosafety principles and policies and to illustrate the technology and process pathways of the core l...

  16. An integrated lean-methods approach to hospital facilities redesign.

    Science.gov (United States)

    Nicholas, John

    2012-01-01

    Lean production methods for eliminating waste and improving processes in manufacturing are now being applied in healthcare. As the author shows, the methods are appropriate for redesigning hospital facilities. When used in an integrated manner and employing teams of mostly clinicians, the methods produce facility designs that are custom-fit to patient needs and caregiver work processes, and reduce operational costs. The author reviews lean methods and an approach for integrating them in the redesign of hospital facilities. A case example of the redesign of an emergency department shows the feasibility and benefits of the approach.

  17. Natural circulation in an integral CANDU test facility

    International Nuclear Information System (INIS)

    Ingham, P.J.; Sanderson, T.V.; Luxat, J.C.; Melnyk, A.J.

    2000-01-01

    Over 70 single- and two-phase natural circulation experiments have been completed in the RD-14M facility, an integral CANDU thermalhydraulic test loop. This paper describes the RD-14M facility and provides an overview of the impact of key parameters on the results of natural circulation experiments. Particular emphasis will be on phenomena which led to heat up at high system inventories in a small subset of experiments. Clarification of misunderstandings in a recently published comparison of the effectiveness of natural circulation flows in RD-14M to integral facilities simulating other reactor geometries will also be provided. (author)

  18. Westinghouse integrated cementation facility. Smart process automation minimizing secondary waste

    International Nuclear Information System (INIS)

    Fehrmann, H.; Jacobs, T.; Aign, J.

    2015-01-01

    The Westinghouse Cementation Facility described in this paper is an example for a typical standardized turnkey project in the area of waste management. The facility is able to handle NPP waste such as evaporator concentrates, spent resins and filter cartridges. The facility scope covers all equipment required for a fully integrated system including all required auxiliary equipment for hydraulic, pneumatic and electric control system. The control system is based on actual PLC technology and the process is highly automated. The equipment is designed to be remotely operated, under radiation exposure conditions. 4 cementation facilities have been built for new CPR-1000 nuclear power stations in China

  19. Design of an integrated non-destructive plutonium assay facility

    International Nuclear Information System (INIS)

    Moore, C.B.

    1984-01-01

    The Department of Energy requires improved technology for nuclear materials accounting as an essential part of new plutonium processing facilities. New facilities are being constructed at the Savannah River Plant by the Du Pont Company, Operating Contractor, to recover plutonium from scrap and waste material generated at SRP and other DOE contract processing facilities. This paper covers design concepts and planning required to incorporate state-of-the-art plutonium assay instruments developed at several national laboratories into an integrated, at-line nuclear material accounting facility operating in the production area. 3 figures

  20. Microgrids | Energy Systems Integration Facility | NREL

    Science.gov (United States)

    . Diesel generators: because diesel generators are traditional microgrid components, three different generator sets with various control options are available for microgrid integration efforts. DC power supplies: the ESIF's full suite of DC simulation capability includes a 1.5-MW photovoltaic (PV) simulator

  1. Double-shell tank waste transfer facilities integrity assessment plan

    International Nuclear Information System (INIS)

    Hundal, T.S.

    1998-01-01

    This document presents the integrity assessment plan for the existing double-shell tank waste transfer facilities system in the 200 East and 200 West Areas of Hanford Site. This plan identifies and proposes the integrity assessment elements and techniques to be performed for each facility. The integrity assessments of existing tank systems that stores or treats dangerous waste is required to be performed to be in compliance with the Washington State Department of Ecology Dangerous Waste Regulations, Washington Administrative Code WAC-173-303-640 requirements

  2. Criticality safety considerations. Integral Monitored Retrievable Storage (MRS) Facility

    International Nuclear Information System (INIS)

    1986-09-01

    This report summarizes the criticality analysis performed to address criticality safety concerns and to support facility design during the conceptual design phase of the Monitored Retrievable Storage (MRS) Facility. The report addresses the criticality safety concerns, the design features of the facility relative to criticality, and the results of the analysis of both normal operating and hypothetical off-normal conditions. Key references are provided (Appendix C) if additional information is desired by the reader. The MRS Facility design was developed and the related analysis was performed in accordance with the MRS Facility Functional Design Criteria and the Basis for Design. The detailed description and calculations are documented in the Integral MRS Facility Conceptual Design Report. In addition to the summary portion of this report, explanatary notes for various terms, calculation methodology, and design parameters are presented in Appendix A. Appendix B provides a brief glossary of technical terms

  3. Evaluation of scaling concepts for integral system test facilities

    International Nuclear Information System (INIS)

    Condie, K.G.; Larson, T.K.; Davis, C.B.

    1987-01-01

    A study was conducted by EG and G Idaho, Inc., to identify and technically evaluate potential concepts which will allow the U.S. Nuclear Regulatory Commission to maintain the capability to conduct future integral, thermal-hydraulic facility experiments of interest to light water reactor safety. This paper summarizes the methodology used in the study and presents a rankings for each facility concept relative to its ability to simulate phenomena identified as important in selected reactor transients in Babcock and Wilcox and Westinghouse large pressurized water reactors. Established scaling methodologies are used to develop potential concepts for scaled integral thermal-hydraulic experiment facilities. Concepts selected included: full height, full pressure water; reduced height, reduced pressure water; reduced height, full pressure water; one-tenth linear, full pressure water; and reduced height, full scaled pressure Freon. Results from this study suggest that a facility capable of operating at typical reactor operating conditions will scale most phenomena reasonably well. Local heat transfer phenomena is best scaled by the full height facility, while the reduced height facilities provide better scaling where multi-dimensional phenomena are considered important. Although many phenomena in facilities using Freon or water at nontypical pressure will scale reasonably well, those phenomena which are heavily dependent on quality can be distorted. Furthermore, relation of data produced in facilities operating with nontypical fluids or at nontypical pressures to large plants will be a difficult and time-consuming process

  4. Integral Monitored Retrievable Storage (MRS) Facility conceptual basis for design

    International Nuclear Information System (INIS)

    1985-10-01

    The purpose of the Conceptual Basis for Design is to provide a control document that establishes the basis for executing the conceptual design of the Integral Monitored Retrievable Storage (MRS) Facility. This conceptual design shall provide the basis for preparation of a proposal to Congress by the Department of Energy (DOE) for construction of one or more MRS Facilities for storage of spent nuclear fuel, high-level radioactive waste, and transuranic (TRU) waste. 4 figs., 25 tabs

  5. PANDA: A Multipurpose Integral Test Facility for LWR Safety Investigations

    International Nuclear Information System (INIS)

    Paladino, D.; Dreier, J.

    2012-01-01

    The PANDA facility is a large scale, multicompartmental thermal hydraulic facility suited for investigations related to the safety of current and advanced LWRs. The facility is multipurpose, and the applications cover integral containment response tests, component tests, primary system tests, and separate effect tests. Experimental investigations carried on in the PANDA facility have been embedded in international projects, most of which under the auspices of the EU and OECD and with the support of a large number of organizations (regulatory bodies, technical dupport organizations, national laboratories, electric utilities, industries) worldwide. The paper provides an overview of the research programs performed in the PANDA facility in relation to BWR containment systems and those planned for PWR containment systems.

  6. Integration of facility modeling capabilities for nuclear nonproliferation analysis

    International Nuclear Information System (INIS)

    Burr, Tom; Gorensek, M.B.; Krebs, John; Kress, Reid L.; Lamberti, Vincent; Schoenwald, David; Ward, Richard C.

    2012-01-01

    Developing automated methods for data collection and analysis that can facilitate nuclearnonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facilitymodeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facilitymodeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facilitymodelingcapabilities and illustrates how they could be integrated and utilized for nonproliferationanalysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facilitymodeling tools. After considering a representative sampling of key facilitymodelingcapabilities, the proposed integration framework is illustrated with several examples.

  7. MIMI: multimodality, multiresource, information integration environment for biomedical core facilities.

    Science.gov (United States)

    Szymanski, Jacek; Wilson, David L; Zhang, Guo-Qiang

    2009-10-01

    The rapid expansion of biomedical research has brought substantial scientific and administrative data management challenges to modern core facilities. Scientifically, a core facility must be able to manage experimental workflow and the corresponding set of large and complex scientific data. It must also disseminate experimental data to relevant researchers in a secure and expedient manner that facilitates collaboration and provides support for data interpretation and analysis. Administratively, a core facility must be able to manage the scheduling of its equipment and to maintain a flexible and effective billing system to track material, resource, and personnel costs and charge for services to sustain its operation. It must also have the ability to regularly monitor the usage and performance of its equipment and to provide summary statistics on resources spent on different categories of research. To address these informatics challenges, we introduce a comprehensive system called MIMI (multimodality, multiresource, information integration environment) that integrates the administrative and scientific support of a core facility into a single web-based environment. We report the design, development, and deployment experience of a baseline MIMI system at an imaging core facility and discuss the general applicability of such a system in other types of core facilities. These initial results suggest that MIMI will be a unique, cost-effective approach to addressing the informatics infrastructure needs of core facilities and similar research laboratories.

  8. National Ignition Facility integrated computer control system

    International Nuclear Information System (INIS)

    Van Arsdall, P.J. LLNL

    1998-01-01

    The NIF design team is developing the Integrated Computer Control System (ICCS), which is based on an object-oriented software framework applicable to event-driven control systems. The framework provides an open, extensible architecture that is sufficiently abstract to construct future mission-critical control systems. The ICCS will become operational when the first 8 out of 192 beams are activated in mid 2000. The ICCS consists of 300 front-end processors attached to 60,000 control points coordinated by a supervisory system. Computers running either Solaris or VxWorks are networked over a hybrid configuration of switched fast Ethernet and asynchronous transfer mode (ATM). ATM carries digital motion video from sensors to operator consoles. Supervisory software is constructed by extending the reusable framework components for each specific application. The framework incorporates services for database persistence, system configuration, graphical user interface, status monitoring, event logging, scripting language, alert management, and access control. More than twenty collaborating software applications are derived from the common framework. The framework is interoperable among different kinds of computers and functions as a plug-in software bus by leveraging a common object request brokering architecture (CORBA). CORBA transparently distributes the software objects across the network. Because of the pivotal role played, CORBA was tested to ensure adequate performance

  9. Energy Systems Integration News | Energy Systems Integration Facility |

    Science.gov (United States)

    , utilities can operate more efficiently and profitably. That can increase the use of renewable energy sources challenge to utility companies, grid operators, and other stakeholders involved in wind energy integration recording is available from the July 16 webinar "Smart Grid Research at NREL's Energy Systems

  10. Structural integrity monitoring of critical components in nuclear facilities

    International Nuclear Information System (INIS)

    Roth, Maria; Constantinescu, Dan Mihai; Brad, Sebastian; Ducu, Catalin; Malinovschi, Viorel

    2007-01-01

    Full text: The paper presents the results obtained as part of the Project 'Integrated Network for Structural Integrity Monitoring of Critical Components in Nuclear Facilities', RIMIS, a research work underway within the framework of the Ministry of Education and Research Programme 'Research of Excellence'. The main objective of the Project is to constitute a network integrating the national R and D institutes with preoccupations in the structural integrity assessment of critical components in the nuclear facilities operating in Romania, in order to elaborate a specific procedure for this field. The degradation mechanisms of the structural materials used in the CANDU type reactors, operated by Unit 1 and Unit 2 at Cernavoda (pressure tubes, fuel elements sheaths, steam generator tubing) and in the nuclear facilities relating to reactors of this type as, for instance, the Hydrogen Isotopes Separation facility, will be investigated. The development of a flexible procedure will offer the opportunity to extend the applications to other structural materials used in the nuclear field and in the non-nuclear fields as well, in cooperation with other institutes involved in the developed network. The expected results of the project will allow the integration of the network developed at national level in the structures of similar networks operating within the EU, the enhancement of the scientific importance of Romanian R and D organizations as well as the increase of our country's contribution in solving the major issues of the nuclear field. (authors)

  11. Energy Systems Integration Facility (ESIF) Facility Stewardship Plan: Revision 2.1

    Energy Technology Data Exchange (ETDEWEB)

    Torres, Juan [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Anderson, Art [National Renewable Energy Laboratory (NREL), Golden, CO (United States)

    2018-01-02

    The U.S. Department of Energy (DOE), Office of Energy Efficiency and Renewable Energy (EERE), has established the Energy Systems Integration Facility (ESIF) on the campus of the National Renewable Energy Laboratory (NREL) and has designated it as a DOE user facility. This 182,500-ft2 research facility provides state-of-the-art laboratory and support infrastructure to optimize the design and performance of electrical, thermal, fuel, and information technologies and systems at scale. This Facility Stewardship Plan provides DOE and other decision makers with information about the existing and expected capabilities of the ESIF and the expected performance metrics to be applied to ESIF operations. This plan is a living document that will be updated and refined throughout the lifetime of the facility.

  12. Integrated biofuel facility, with carbon dioxide consumption and power generation

    Energy Technology Data Exchange (ETDEWEB)

    Powell, E.E.; Hill, G.A. [Saskatchewan Univ., Saskatoon, SK (Canada). Dept. of Chemical Engineering

    2009-07-01

    This presentation provided details of an economical design for a large-scale integrated biofuel facility for coupled production of bioethanol and biodiesel, with carbon dioxide capture and power generation. Several designs were suggested for both batch and continuous culture operations, taking into account all costs and revenues associated with the complete plant integration. The microalgae species Chlorella vulgaris was cultivated in a novel photobioreactor (PBR) in order to consume industrial carbon dioxide (CO{sub 2}). This photosynthetic culture can also act as a biocathode in a microbial fuel cell (MFC), which when coupled to a typical yeast anodic half cell, results in a complete biological MFC. The photosynthetic MFC produces electricity as well as valuable biomass and by-products. The use of this novel photosynthetic microalgae cathodic half cell in an integrated biofuel facility was discussed. A series of novel PBRs for continuous operation can be integrated into a large-scale bioethanol facility, where the PBRs serve as cathodic half cells and are coupled to the existing yeast fermentation tanks which act as anodic half cells. These coupled MFCs generate electricity for use within the biofuel facility. The microalgae growth provides oil for biodiesel production, in addition to the bioethanol from the yeast fermentation. The photosynthetic cultivation in the cathodic PBR also requires carbon dioxide, resulting in consumption of carbon dioxide from bioethanol production. The paper also discussed the effect of plant design on net present worth and internal rate of return. tabs., figs.

  13. Multiloop Integral System Test (MIST): MIST Facility Functional Specification

    International Nuclear Information System (INIS)

    Habib, T.F.; Koksal, C.G.; Moskal, T.E.; Rush, G.C.; Gloudemans, J.R.

    1991-04-01

    The Multiloop Integral System Test (MIST) is part of a multiphase program started in 1983 to address small-break loss-of-coolant accidents (SBLOCAs) specific to Babcock and Wilcox designed plants. MIST is sponsored by the US Nuclear Regulatory Commission, the Babcock ampersand Wilcox Owners Group, the Electric Power Research Institute, and Babcock and Wilcox. The unique features of the Babcock and Wilcox design, specifically the hot leg U-bends and steam generators, prevented the use of existing integral system data or existing integral facilities to address the thermal-hydraulic SBLOCA questions. MIST was specifically designed and constructed for this program, and an existing facility -- the Once Through Integral System (OTIS) -- was also used. Data from MIST and OTIS are used to benchmark the adequacy of system codes, such as RELAP5 and TRAC, for predicting abnormal plant transients. The MIST Functional Specification documents as-built design features, dimensions, instrumentation, and test approach. It also presents the scaling basis for the facility and serves to define the scope of work for the facility design and construction. 13 refs., 112 figs., 38 tabs

  14. BWR Full Integral Simulation Test (FIST) program: facility description report

    International Nuclear Information System (INIS)

    Stephens, A.G.

    1984-09-01

    A new boiling water reactor safety test facility (FIST, Full Integral Simulation Test) is described. It will be used to investigate small breaks and operational transients and to tie results from such tests to earlier large-break test results determined in the TLTA. The new facility's full height and prototypical components constitute a major scaling improvement over earlier test facilities. A heated feedwater system, permitting steady-state operation, and a large increase in the number of measurements are other significant improvements. The program background is outlined and program objectives defined. The design basis is presented together with a detailed, complete description of the facility and measurements to be made. An extensive component scaling analysis and prediction of performance are presented

  15. Australian national networked tele-test facility for integrated systems

    Science.gov (United States)

    Eshraghian, Kamran; Lachowicz, Stefan W.; Eshraghian, Sholeh

    2001-11-01

    The Australian Commonwealth government recently announced a grant of 4.75 million as part of a 13.5 million program to establish a world class networked IC tele-test facility in Australia. The facility will be based on a state-of-the-art semiconductor tester located at Edith Cowan University in Perth that will operate as a virtual centre spanning Australia. Satellite nodes will be located at the University of Western Australia, Griffith University, Macquarie University, Victoria University and the University of Adelaide. The facility will provide vital equipment to take Australia to the frontier of critically important and expanding fields in microelectronics research and development. The tele-test network will provide state of the art environment for the electronics and microelectronics research and the industry community around Australia to test and prototype Very Large Scale Integrated (VLSI) circuits and other System On a Chip (SOC) devices, prior to moving to the manufacturing stage. Such testing is absolutely essential to ensure that the device performs to specification. This paper presents the current context in which the testing facility is being established, the methodologies behind the integration of design and test strategies and the target shape of the tele-testing Facility.

  16. Annual Summary of the Integrated Disposal Facility Performance Assessment 2012

    Energy Technology Data Exchange (ETDEWEB)

    Khaleel, R. [INTERA, Austin, TX (United States); Nichols, W. E. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

    2012-12-27

    An annual summary of the adequacy of the Hanford Immobilized Low-Activity Waste (ILAW) Performance Assessment (PA) is required each year (DOE O 435.1 Chg 1,1 DOE M 435.1-1 Chg 1;2 and DOE/ORP-2000-013). The most recently approved PA is DOE/ORP-2000-24.4 The ILAW PA evaluated the adequacy of the ILAW disposal facility, now referred to as the Integrated Disposal Facility (IDF), for the safe disposal of vitrified Hanford Site tank waste.

  17. ICAT: Integrating data infrastructure for facilities based science

    International Nuclear Information System (INIS)

    Flannery, Damian; Matthews, Brian; Griffin, Tom; Bicarregui, Juan; Gleaves, Michael; Lerusse, Laurent; Downing, Roger; Ashton, Alun; Sufi, Shoaib; Drinkwater, Glen; Kleese van Dam, Kerstin

    2009-01-01

    ICAT: Integrating data infrastructure for facilities based science Damian Flannery, Brian Matthews, Tom Griffin, Juan Bicarregui, Michael Gleaves, Laurent Lerusse, Roger Downing, Alun Ashton, Shoaib Sufi, Glen Drinkwater, Kerstin Kleese Abstract Scientific facilities, in particular large-scale photon and neutron sources, have demanding requirements to manage the increasing quantities of experimental data they generate in a systematic and secure way. In this paper, we describe the ICAT infrastructure for cataloguing facility generated experimental data which has been in development within STFC and DLS for several years. We consider the factors which have influenced its design and describe its architecture and metadata model, a key tool in the management of data. We go on to give an outline of its current implementation and use, with plans for its future development.

  18. Vehicle Testing and Integration Facility; NREL (National Renewable Energy Laboratory)

    Energy Technology Data Exchange (ETDEWEB)

    None

    2015-03-02

    Engineers at the National Renewable Energy Laboratory’s (NREL’s) Vehicle Testing and Integration Facility (VTIF) are developing strategies to address two separate but equally crucial areas of research: meeting the demands of electric vehicle (EV) grid integration and minimizing fuel consumption related to vehicle climate control. Dedicated to renewable and energy-efficient solutions, the VTIF showcases technologies and systems designed to increase the viability of sustainably powered vehicles. NREL researchers instrument every class of on-road vehicle, conduct hardware and software validation for EV components and accessories, and develop analysis tools and technology for the Department of Energy, other government agencies, and industry partners.

  19. Study on system integration of robots operated in nuclear fusion facility and nuclear power plant facilities

    International Nuclear Information System (INIS)

    Oka, Kiyoshi

    2004-07-01

    A present robot is required to apply to many fields such as amusement, welfare and protection against disasters. The are however only limited numbers of the robots, which can work under the actual conditions as a robot system. It is caused by the following reasons: (1) the robot system cannot be realized by the only collection of the elemental technologies, (2) the performance of the robot is determined by that of the integrated system composed of the complicated elements with many functions, and (3) the respective elements have to be optimized in the integrated robot system with a well balance among them, through their examination, adjustment and improvement. Therefore, the system integration of the robot composed of a large number of elements is the most critical issue to realize the robot system for actual use. In the present paper, I describe the necessary approaches and elemental technologies to solve the issues on the system integration of the typical robot systems for maintenance in the nuclear fusion facility and rescue in the accident of the nuclear power plant facilities. These robots work under the intense radiation condition and restricted space in place of human. In particular, I propose a new approach to realize the system integration of the robot for actual use from the viewpoints of not only the environment and working conditions but also the restructure and optimization of the required elemental technologies with a well balance in the robot system. Based on the above approach, I have a contribution to realize the robot systems working under the actual conditions for maintenance in the nuclear fusion facility and rescue in the accident of the nuclear power plant facilities. (author)

  20. An integral effect test facility of the SMART, SMART ITL

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hyun Sik; Moon, Sang Ki; Kim, Yeon Sik; Cho, Seok; Choi, Ki Yong; Bae, Hwang; Kim, Dong Eok; Choi, Nam Hyun; Min, Kyoung Ho; Ko, Yung Joo; Shin, Yong Cheol; Park, Rae Joon; Lee, Won Jae; Song, Chul Hwa; Yi, Sung Jae [KAERI, Daejeon (Korea, Republic of)

    2012-10-15

    SMART (System integrated Modular Advanced ReacTor) is a 330 MWth integral pressurized water reactor (iPWR) developed by KAERI and had obtained standard design approval (SDA) from Korean regulatory authority on July 2012. In this SMART design main components including a pressurizer, reactor coolant pumps and steam generators are installed in a reactor pressure vessel without any large connecting pipes. As the LBLOCA scenario is inherently excluded, its safety systems could be simplified only to ensure the safety during the SBLOCA scenarios and the other system transients. An integral effect test loop for the SMART (SMART ITL), or called as FESTA, had been designed to simulate the integral thermal hydraulic behavior of the SMART. The objectives of the SMART ITL are to investigate and understand the integral performance of reactor systems and components and the thermal hydraulic phenomena occurred in the system during normal, abnormal and emergency conditions, and to verify the system safety during various design basis events of the SMART. The integral effect test data will also be used to validate the related thermal hydraulic models of the safety analysis code such as TASS/SMR S, which is used for performance and accident analysis of the SMART design. This paper introduces the scaling analysis and scientific design of the integral test facility of the SMART, SMART ITL and its scaling analysis results.

  1. A Supply Chain Design Problem Integrated Facility Unavailabilities Management

    Directory of Open Access Journals (Sweden)

    Fouad Maliki

    2016-08-01

    Full Text Available A supply chain is a set of facilities connected together in order to provide products to customers. The supply chain is subject to random failures caused by different factors which cause the unavailability of some sites. Given the current economic context, the management of these unavailabilities is becoming a strategic choice to ensure the desired reliability and availability levels of the different supply chain facilities. In this work, we treat two problems related to the field of supply chain, namely the design and unavailabilities management of logistics facilities. Specifically, we consider a stochastic distribution network with consideration of suppliers' selection, distribution centres location (DCs decisions and DCs’ unavailabilities management. Two resolution approaches are proposed. The first approach called non-integrated consists on define the optimal supply chain structure using an optimization approach based on genetic algorithms (GA, then to simulate the supply chain performance with the presence of DCs failures. The second approach called integrated approach is to consider the design of the supply chain problem and unavailabilities management of DCs in the same model. Note that, we replace each unavailable DC by performing a reallocation using GA in the two approaches. The obtained results of the two approaches are detailed and compared showing their effectiveness.

  2. Integrated Disposal Facility FY2011 Glass Testing Summary Report

    International Nuclear Information System (INIS)

    Pierce, Eric M.; Bacon, Diana H.; Kerisit, Sebastien N.; Windisch, Charles F.; Cantrell, Kirk J.; Valenta, Michelle M.; Burton, Sarah D.; Westsik, Joseph H.

    2011-01-01

    Pacific Northwest National Laboratory was contracted by Washington River Protection Solutions, LLC to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility (e.g., source term). Vitrifying the low-activity waste at Hanford is expected to generate over 1.6 x 10 5 m 3 of glass (Certa and Wells 2010). The volume of immobilized low-activity waste (ILAW) at Hanford is the largest in the DOE complex and is one of the largest inventories (approximately 8.9 x 10 14 Bq total activity) of long-lived radionuclides, principally 99 Tc (t 1/2 = 2.1 x 10 5 ), planned for disposal in a low-level waste (LLW) facility. Before the ILAW can be disposed, DOE must conduct a performance assessment (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program PNNL is implementing a strategy, consisting of experimentation and modeling, in order to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. The purpose of this report is to summarize the progress made in fiscal year (FY) 2011 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of low-activity waste glasses.

  3. Integrated Disposal Facility FY2011 Glass Testing Summary Report

    Energy Technology Data Exchange (ETDEWEB)

    Pierce, Eric M.; Bacon, Diana H.; Kerisit, Sebastien N.; Windisch, Charles F.; Cantrell, Kirk J.; Valenta, Michelle M.; Burton, Sarah D.; Westsik, Joseph H.

    2011-09-29

    Pacific Northwest National Laboratory was contracted by Washington River Protection Solutions, LLC to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility (e.g., source term). Vitrifying the low-activity waste at Hanford is expected to generate over 1.6 x 10{sup 5} m{sup 3} of glass (Certa and Wells 2010). The volume of immobilized low-activity waste (ILAW) at Hanford is the largest in the DOE complex and is one of the largest inventories (approximately 8.9 x 10{sup 14} Bq total activity) of long-lived radionuclides, principally {sup 99}Tc (t{sub 1/2} = 2.1 x 10{sup 5}), planned for disposal in a low-level waste (LLW) facility. Before the ILAW can be disposed, DOE must conduct a performance assessment (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program PNNL is implementing a strategy, consisting of experimentation and modeling, in order to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. The purpose of this report is to summarize the progress made in fiscal year (FY) 2011 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of low-activity waste glasses.

  4. Design of integrated safeguards systems for nuclear facilities

    International Nuclear Information System (INIS)

    de Montmollin, J.M.; Walton, R.B.

    1978-06-01

    Safeguards systems that are capable of countering postulated threats to nuclear facilities must be closely integrated with plant layout and processes if they are to be effective and if potentially-severe impacts on plant operations are to be averted. This paper describes a facilities safeguards system suitable for production plant, in which the traditional elements of physical protection and periodic material-balance accounting are extended and augmented to provide close control of material flows. Discrete material items are subjected to direct, overriding physical control where appropriate. Materials in closely-coupled process streams are protected by on-line NDA and weight measurements, with rapid computation of material balances to provide immediate indication of large-scale diversion. The system provides information and actions at the safeguards/operations interface

  5. Design of integrated safeguards systems for nuclear facilities

    International Nuclear Information System (INIS)

    de Montmollin, J.M.; Walton, R.B.

    1976-01-01

    Safeguards systems that are capable of countering postulated threats to nuclear facilities must be closely integrated with plant layout and processes if they are to be effective and if potentially severe impacts on plant operations are to be averted. A facilities safeguards system suitable for a production plant is described in which the traditional elements of physical protection and periodic material-balance accounting are extended and augmented to provide close control of material flows. Discrete material items are subjected to direct, overriding physical control where appropriate. Materials in closely coupled process streams are protected by on-line NDA and weight measurements, with rapid computation of material balances to provide immediate indication of large-scale diversion. The system provides an information and actions at the safeguards/operations interface

  6. An integrated approach for facilities planning by ELECTRE method

    Science.gov (United States)

    Elbishari, E. M. Y.; Hazza, M. H. F. Al; Adesta, E. Y. T.; Rahman, Nur Salihah Binti Abdul

    2018-01-01

    Facility planning is concerned with the design, layout, and accommodation of people, machines and activities of a system. Most of the researchers try to investigate the production area layout and the related facilities. However, few of them try to investigate the relationship between the production space and its relationship with service departments. The aim of this research to is to integrate different approaches in order to evaluate, analyse and select the best facilities planning method that able to explain the relationship between the production area and other supporting departments and its effect on human efforts. To achieve the objective of this research two different approaches have been integrated: Apple’s layout procedure as one of the effective tools in planning factories, ELECTRE method as one of the Multi Criteria Decision Making methods (MCDM) to minimize the risk of getting poor facilities planning. Dalia industries have been selected as a case study to implement our integration the factory have been divided two main different area: the whole facility (layout A), and the manufacturing area (layout B). This article will be concerned with the manufacturing area layout (Layout B). After analysing the data gathered, the manufacturing area was divided into 10 activities. There are five factors that the alternative were compared upon which are: Inter department satisfactory level, total distance travelled for workers, total distance travelled for the product, total time travelled for the workers, and total time travelled for the product. Three different layout alternatives have been developed in addition to the original layouts. Apple’s layout procedure was used to study and evaluate the different alternatives layouts, the study and evaluation of the layouts was done by calculating scores for each of the factors. After obtaining the scores from evaluating the layouts, ELECTRE method was used to compare the proposed alternatives with each other and with

  7. MHD Integrated Topping Cycle Project

    Science.gov (United States)

    1993-04-01

    Manufacture, assembly, and checkout of combustion subsystem hardware was completed and the hardware was delivered to CDIF along with the water electrical isolators. A successful nozzle proof test was concluded; its purpose was to evaluate adequacy of the nozzle structure and sealing of sidewall-to-electrode wall joints, water tubes, and stud and wire penetrations at operating pressure. Design modifications to spare channel inlet frame were made to enable iron oxide injection. Results of tests in the CDIF 1A1 channel which compared effect of different cathode wall iron oxide injection locations indicated that injection through the side port may be more effective, particularly if one of the two ports becomes clogged. Design confirmation testing of a pneumatically driven ram to clear a plugged iron oxide injector tip was performed. Manufacture of spare and replacement parts for 1A4 channel and diffuser was begun. Construction of the cathode power cabinets and associated control system was completed. Hot-fire checkout series was completed for the combustion subsystem; 16.8 thermal hours were accumulated during seven tests. This test series demonstrated adequacy of overall cooling of combustion subsystem and provided an initial evaluation of heat losses and slagging characteristics. Several major facility activities at the CDIF were accomplished including installation and testing of new iron oxide pumps, initial on-line checkout of coal feed system modifications, modification of seed system including replacement of silo rotary feeder, installation of new filter receiver on the silo, conversion of fly ash bin to dust collector, removal of all of the electrical wiring (used for 1A1 channel) between the channel and HVR in order to install 1A4 wiring, and installation of the 1A4 channel.

  8. Integrated O&M for energy generation and exchange facilities

    International Nuclear Information System (INIS)

    2016-01-01

    Ingeteam Service, part of the Ingeteam Group, is a leading company in the provision of integrated O&M services at energy generation and exchange facilities worldwide. From its head office in the Albacete Science and Technology Park, it manages the work of the 1,300 employees that make up its global workforce, rendering services to wind farms, PV installations and power generation plants. In addition, it maintains an active participation strategy in a range of R&D+i programmes that improve the existing technologies and are geared towards new production systems and new diagnostic techniques, applied to renewables installation maintenance. (Author)

  9. Integrated network for structural integrity monitoring of critical components in nuclear facilities, RIMIS

    International Nuclear Information System (INIS)

    Roth, Maria; Constantinescu, Dan Mihai; Brad, Sebastian; Ducu, Catalin; Malinovschi, Viorel

    2008-01-01

    The round table aims to join specialists working in the research area of the Romanian R and D Institutes and Universities involved in structural integrity assessment of materials, especially those working in the nuclear field, together with the representatives of the end user, the Cernavoda NPP. This scientific event will offer the opportunity to disseminate the theoretical, experimental and modelling activities, carried out to date, in the framework of the National Program 'Research of Excellence', Module I 2006-2008, managed by the National Authority for Scientific Research. Entitled 'Integrated Network for Structural Integrity Monitoring of Critical Components in Nuclear Facilities, RIMIS, the project has two main objectives: 1. - to elaborate a procedure applicable to the structural integrity assessment of critical components used in Romanian nuclear facilities (CANDU type Reactor, Hydrogen Isotopes Separation installations); 2. - to integrate the national networking into a similar one of European level, and to enhance the scientific significance of Romanian R and D organisations as well as to increase the contribution in solving major issues of the nuclear field. The topics of the round table will be focused on: 1. Development of a Structural Integrity Assessment Methodology applicable to the nuclear facilities components; 2. Experimental investigation methods and procedures; 3. Numeric simulation of nuclear components behaviour; 4. Further activities to finalize the assessment procedure. Also participations and contributions to sustain the activity in the European Network NULIFE, FP6 will be discussed. (authors)

  10. Consistent Posttest Calculations for LOCA Scenarios in LOBI Integral Facility

    Directory of Open Access Journals (Sweden)

    F. Reventós

    2012-01-01

    Full Text Available Integral test facilities (ITFs are one of the main tools for the validation of best estimate thermalhydraulic system codes. The experimental data are also of great value when compared to the experiment-scaled conditions in a full NPP. The LOBI was a single plus a triple-loop (simulated by one loop test facility electrically heated to simulate a 1300 MWe PWR. The scaling factor was 712 for the core power, volume, and mass flow. Primary and secondary sides contained all main active elements. Tests were performed for the characterization of phenomenologies relevant to large and small break LOCAs and special transients in PWRs. The paper presents the results of three posttest calculations of LOBI experiments. The selected experiments are BL-30, BL-44, and A1-84. They are LOCA scenarios of different break sizes and with different availability of safety injection components. The goal of the analysis is to improve the knowledge of the phenomena occurred in the facility in order to use it in further studies related to qualifying nodalizations of actual plants or to establish accuracy data bases for uncertainty methodologies. An example of procedure of implementing changes in a common nodalization valid for simulating tests occurred in a specific ITF is presented along with its confirmation based on posttests results.

  11. Integrated Disposal Facility FY 2012 Glass Testing Summary Report

    Energy Technology Data Exchange (ETDEWEB)

    Pierce, Eric M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Kerisit, Sebastien N. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Krogstad, Eirik J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Burton, Sarah D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Bjornstad, Bruce N. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Freedman, Vicky L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Cantrell, Kirk J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Snyder, Michelle MV [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Crum, Jarrod V. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Westsik, Joseph H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2013-03-29

    PNNL is conducting work to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility for Hanford immobilized low-activity waste (ILAW). Before the ILAW can be disposed, DOE must conduct a performance assessment (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program, PNNL is implementing a strategy, consisting of experimentation and modeling, to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. Key activities in FY12 include upgrading the STOMP/eSTOMP codes to do near-field modeling, geochemical modeling of PCT tests to determine the reaction network to be used in the STOMP codes, conducting PUF tests on selected glasses to simulate and accelerate glass weathering, developing a Monte Carlo simulation tool to predict the characteristics of the weathered glass reaction layer as a function of glass composition, and characterizing glasses and soil samples exhumed from an 8-year lysimeter test. The purpose of this report is to summarize the progress made in fiscal year (FY) 2012 and the first quarter of FY 2013 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of LAW glasses.

  12. EPICS - MDSplus integration in the ITER Neutral Beam Test Facility

    International Nuclear Information System (INIS)

    Luchetta, Adriano; Manduchi, Gabriele; Barbalace, Antonio; Soppelsa, Anton; Taliercio, Cesare

    2011-01-01

    SPIDER, the ITER-size ion-source test bed in the ITER Neutral Beam Test Facility, is a fusion device requiring a complex central system to provide control and data acquisition, referred to as CODAS. The CODAS software architecture will rely on EPICS and MDSplus, two open-source, collaborative software frameworks, targeted at control and data acquisition, respectively. EPICS has been selected as ITER CODAC middleware and, as the final deliverable of the Neutral Beam Test Facility is the procurement of the ITER Heating Neutral Beam Injector, we decided to adopt this ITER technology. MDSplus is a software package for data management, supporting advanced concepts, such as platform and underlying hardware independence, self description data, and data driven model. The combined use of EPICS and MDSplus is not new in fusion, but their level of integration will be new in SPIDER, achieved by a more refined data access layer. The paper presents the integration software to use effectively EPICS and MDSplus, including the definition of appropriate EPICS records to interact with MDSplus. The MDSplus and EPICS archive concepts are also compared on the basis of performance tests and data streaming is investigated by ad-hoc measurements.

  13. Integration of radiation and physical safety in large radiator facilities

    International Nuclear Information System (INIS)

    Lima, P.P.M.; Benedito, A.M.; Lima, C.M.A.; Silva, F.C.A. da

    2017-01-01

    Growing international concern about radioactive sources after the Sept. 11, 2001 event has led to a strengthening of physical safety. There is evidence that the illicit use of radioactive sources is a real possibility and may result in harmful radiological consequences for the population and the environment. In Brazil there are about 2000 medical, industrial and research facilities with radioactive sources, of which 400 are Category 1 and 2 classified by the - International Atomic Energy Agency - AIEA, where large irradiators occupy a prominent position due to the very high cobalt-60 activities. The radiological safety is well established in these facilities, due to the intense work of the authorities in the Country. In the paper the main aspects on radiological and physical safety applied in the large radiators are presented, in order to integrate both concepts for the benefit of the safety as a whole. The research showed that the items related to radiation safety are well defined, for example, the tests on the access control devices to the irradiation room. On the other hand, items related to physical security, such as effective control of access to the company, use of safety cameras throughout the company, are not yet fully incorporated. Integration of radiation and physical safety is fundamental for total safety. The elaboration of a Brazilian regulation on the subject is of extreme importance

  14. Derivation of integral energy balance for the manotea facility

    Energy Technology Data Exchange (ETDEWEB)

    Pollman, Anthony, E-mail: pollman@nps.edu [Mechanical and Aeronautical Engineering Department, United States Naval Postgraduate School, Monterey, CA 93943 (United States); Marzo, Marino di [Fire Protection Engineering Department, University of Maryland, College Park, MD 20742 (United States)

    2013-12-15

    Highlights: • An integral energy balance was derived for the MANOTEA facility. • A second equation was derived which frames transients in terms of inventory alone. • Both equations were implemented and showed good agreement with experimental data. • The equations capture the physical mechanisms behind MANOTEA transients. • Physical understanding is required in order to properly model these transients with TRACE. - Abstract: Rapid-condensation-induced fluid motion occurs in several nuclear reactor accident sequences, as well as during normal operation. Modeling these events is central to our ability to regulate and ensure safe reactor operations. The UMD-USNA Near One-dimensional Transient Experimental Apparatus (MANOTEA) was constructed in order to create a rapid-condensation dataset for subsequent comparison to TRACE output. This paper outlines a derivation of the energy balance for the facility. A path integral based on mass and energy, rather than fluid mechanical, considerations is derived in order to characterize the physical mechanisms governing MANOTEA transients. This equation is further simplified to obtain an expression that frames transients in term of liquid inventory alone. Using data obtained from an actual transient, the path integral is implemented using three variables (change in liquid inventory, liquid inventory as a function of time, and change in metal temperature) to predict the outcome of a fourth independently measured variable (condenser pressure as a function of time). The implementation yields a very good approximation of the actual data. The inventory equation is also implemented and shows reasonable agreement. These equations, and the physical intuition that they yield, are key to properly characterizing MANOTEA transients and any subsequent modeling efforts.

  15. Summarisation of construction and commissioning experience for nuclear power integrated test facility

    International Nuclear Information System (INIS)

    Xiao Zejun; Jia Dounan; Jiang Xulun; Chen Bingde

    2003-01-01

    Since the foundation of Nuclear Power Institute of China, it has successively designed various engineering experimental facilities, and constructed nuclear power experimental research base, and accumulated rich construction experiences of nuclear power integrated test facility. The author presents experience on design, construction and commissioning of nuclear power integrated test facility

  16. The development of functional requirement for integrated test facility

    International Nuclear Information System (INIS)

    Sim, B.S.; Oh, I.S.; Cha, K.H.; Lee, H.C.

    1994-01-01

    An Integrated Test Facility (ITF) is a human factors experimental environment comprised of a nuclear power plant function simulator, man-machine interfaces (MMI), human performance recording systems, and signal control and data analysis systems. In this study, we are going to describe how the functional requirements are developed by identification of both the characteristics of generic advanced control rooms and the research topics of world-wide research interest in human factors community. The functional requirements of user interface developed in this paper together with those of the other elements will be used for the design and implementation of the ITF which will serve as the basis for experimental research on a line of human factors topics. (author). 15 refs, 1 fig

  17. An Integration Testing Facility for the CERN Accelerator Controls System

    CERN Document Server

    Stapley, N; Bau, J C; Deghaye, S; Dehavay, C; Sliwinski, W; Sobczak, M

    2009-01-01

    A major effort has been invested in the design, development, and deployment of the LHC Control System. This large control system is made up of a set of core components and dependencies, which although tested individually, are often not able to be tested together on a system capable of representing the complete control system environment, including hardware. Furthermore this control system is being adapted and applied to CERN's whole accelerator complex, and in particular for the forthcoming renovation of the PS accelerators. To ensure quality is maintained as the system evolves, and toimprove defect prevention, the Controls Group launched a project to provide a dedicated facility for continuous, automated, integration testing of its core components to incorporate into its production process. We describe the project, initial lessons from its application, status, and future directions.

  18. MEASURE: An integrated data-analysis and model identification facility

    Science.gov (United States)

    Singh, Jaidip; Iyer, Ravi K.

    1990-01-01

    The first phase of the development of MEASURE, an integrated data analysis and model identification facility is described. The facility takes system activity data as input and produces as output representative behavioral models of the system in near real time. In addition a wide range of statistical characteristics of the measured system are also available. The usage of the system is illustrated on data collected via software instrumentation of a network of SUN workstations at the University of Illinois. Initially, statistical clustering is used to identify high density regions of resource-usage in a given environment. The identified regions form the states for building a state-transition model to evaluate system and program performance in real time. The model is then solved to obtain useful parameters such as the response-time distribution and the mean waiting time in each state. A graphical interface which displays the identified models and their characteristics (with real time updates) was also developed. The results provide an understanding of the resource-usage in the system under various workload conditions. This work is targeted for a testbed of UNIX workstations with the initial phase ported to SUN workstations on the NASA, Ames Research Center Advanced Automation Testbed.

  19. Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

    International Nuclear Information System (INIS)

    1985-09-01

    This report presents a summary design description of the Conceptual Design for an Integral Monitored Retrievable Storage (MRS) Facility, as prepared by The Ralph M. Parsons Company under an A-E services contract with the Richland Operations Office of the Department of Energy. More detailed design requirements and design data are set forth in the Basis for Design and Design Report, bound under separate cover and available for reference by those desiring such information. The design data provided in this Design Report Executive Summary, the Basis for Design, and the Design Report include contributions by the Waste Technology Services Division of Westinghouse Electric Corporation (WEC), which was responsible for the development of the waste receiving, packaging, and storage systems, and Golder Associates Incorporated (GAI), which supported the design development with program studies. The MRS Facility design requirements, which formed the basis for the design effort, were prepared by Pacific Northwest Laboratory for the US Department of Energy, Richland Operations Office, in the form of a Functional Design Criteria (FDC) document, Rev. 4, August 1985. 9 figs., 6 tabs

  20. Integrated Disposal Facility FY2010 Glass Testing Summary Report

    International Nuclear Information System (INIS)

    Pierce, Eric M.; Bacon, Diana H.; Kerisit, Sebastien N.; Windisch, Charles F.; Cantrell, Kirk J.; Valenta, Michelle M.; Burton, Sarah D.; Serne, R. Jeffrey; Mattigod, Shas V.

    2010-01-01

    Pacific Northwest National Laboratory was contracted by Washington River Protection Solutions, LLC to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility (e.g., source term). Vitrifying the low-activity waste at Hanford is expected to generate over 1.6 A - 105 m 3 of glass (Puigh 1999). The volume of immobilized low-activity waste (ILAW) at Hanford is the largest in the DOE complex and is one of the largest inventories (approximately 0.89 A - 1018 Bq total activity) of long-lived radionuclides, principally 99Tc (t1/2 = 2.1 A - 105), planned for disposal in a low-level waste (LLW) facility. Before the ILAW can be disposed, DOE must conduct a performance assessement (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program PNNL is implementing a strategy, consisting of experimentation and modeling, in order to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. The purpose of this report is to summarize the progress made in fiscal year (FY) 2010 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of low-activity waste glasses. The emphasis in FY2010 was the completing an evaluation of the most sensitive kinetic rate law parameters used to predict glass weathering, documented in Bacon and Pierce (2010), and transitioning from the use of the Subsurface Transport Over Reactive Multi-phases to Subsurface Transport Over Multiple Phases computer code for near-field calculations. The FY2010 activities also consisted of developing a Monte Carlo and Geochemical Modeling framework that links glass composition to alteration phase formation by (1) determining the structure of unreacted and reacted glasses for use as input information into Monte Carlo

  1. Integrated Disposal Facility FY2010 Glass Testing Summary Report

    Energy Technology Data Exchange (ETDEWEB)

    Pierce, Eric M.; Bacon, Diana H.; Kerisit, Sebastien N.; Windisch, Charles F.; Cantrell, Kirk J.; Valenta, Michelle M.; Burton, Sarah D.; Serne, R Jeffrey; Mattigod, Shas V.

    2010-09-30

    Pacific Northwest National Laboratory was contracted by Washington River Protection Solutions, LLC to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility (e.g., source term). Vitrifying the low-activity waste at Hanford is expected to generate over 1.6 × 105 m3 of glass (Puigh 1999). The volume of immobilized low-activity waste (ILAW) at Hanford is the largest in the DOE complex and is one of the largest inventories (approximately 0.89 × 1018 Bq total activity) of long-lived radionuclides, principally 99Tc (t1/2 = 2.1 × 105), planned for disposal in a low-level waste (LLW) facility. Before the ILAW can be disposed, DOE must conduct a performance assessement (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program PNNL is implementing a strategy, consisting of experimentation and modeling, in order to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. The purpose of this report is to summarize the progress made in fiscal year (FY) 2010 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of low-activity waste glasses. The emphasis in FY2010 was the completing an evaluation of the most sensitive kinetic rate law parameters used to predict glass weathering, documented in Bacon and Pierce (2010), and transitioning from the use of the Subsurface Transport Over Reactive Multi-phases to Subsurface Transport Over Multiple Phases computer code for near-field calculations. The FY2010 activities also consisted of developing a Monte Carlo and Geochemical Modeling framework that links glass composition to alteration phase formation by 1) determining the structure of unreacted and reacted glasses for use as input information into Monte Carlo

  2. Heterogeneous Electronics – Wafer Level Integration, Packaging, and Assembly Facility

    Data.gov (United States)

    Federal Laboratory Consortium — This facility integrates active electronics with microelectromechanical (MEMS) devices at the miniature system scale. It obviates current size-, weight-, and power...

  3. Integrated social facility location planning for decision support: Accessibility studies provide support to facility location and integration of social service provision

    CSIR Research Space (South Africa)

    Green, Cheri A

    2012-09-01

    Full Text Available for two or more facilities to create an integrated plan for development Step 6 Costing of development plan Case Study Access norms and thresholds guidelines in accessibility analysis Appropriate norms/provision guidelines facilitate both service... access norms and threshold standards ?Test the relationship between service demand and the supply (service capacity) of the facility provision points within a defined catchment area ?Promote the ?right?sizing? of facilities relative to the demand...

  4. Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

    International Nuclear Information System (INIS)

    1985-09-01

    This document, Volume 5 Book 1, contains cost estimate summaries for a monitored retrievable storage (MRS) facility. The cost estimate is based on the engineering performed during the conceptual design phase of the MRS Facility project

  5. Knowledge Management tools integration within DLR's concurrent engineering facility

    Science.gov (United States)

    Lopez, R. P.; Soragavi, G.; Deshmukh, M.; Ludtke, D.

    The complexity of space endeavors has increased the need for Knowledge Management (KM) tools. The concept of KM involves not only the electronic storage of knowledge, but also the process of making this knowledge available, reusable and traceable. Establishing a KM concept within the Concurrent Engineering Facility (CEF) has been a research topic of the German Aerospace Centre (DLR). This paper presents the current KM tools of the CEF: the Software Platform for Organizing and Capturing Knowledge (S.P.O.C.K.), the data model Virtual Satellite (VirSat), and the Simulation Model Library (SimMoLib), and how their usage improved the Concurrent Engineering (CE) process. This paper also exposes the lessons learned from the introduction of KM practices into the CEF and elaborates a roadmap for the further development of KM in CE activities at DLR. The results of the application of the Knowledge Management tools have shown the potential of merging the three software platforms with their functionalities, as the next step towards the fully integration of KM practices into the CE process. VirSat will stay as the main software platform used within a CE study, and S.P.O.C.K. and SimMoLib will be integrated into VirSat. These tools will support the data model as a reference and documentation source, and as an access to simulation and calculation models. The use of KM tools in the CEF aims to become a basic practice during the CE process. The settlement of this practice will result in a much more extended knowledge and experience exchange within the Concurrent Engineering environment and, consequently, the outcome of the studies will comprise higher quality in the design of space systems.

  6. 242-A Evaporator crystallizer facility integrated annual safety appraisal

    International Nuclear Information System (INIS)

    1991-01-01

    This report provides the results of the Fiscal Year (FY) 1991 Annual Integrated Safety Appraisal of the 242-A Evaporator Crystallizer Facility in the Hanford 200 East Area. The appraisal was conducted in December 1990 and January 1991, by the Waste Tank Safety Assurance (WTSA) organizations in conjunction with Radiological Engineering, Criticality Safety, Packaging and Shipping Safety, Emergency Preparedness, Environmental Compliance, and Quality Assurance. Reports of these eight organizations are presented as Sections 2 through 7 of this report. The purpose of the appraisal was to verify that the 242-A Evaporator meets US Department of Energy (DOE) and Westinghouse Hanford Company (WHC) requirements and current industry standards of good practice for the areas being appraised. A further purpose was to identify areas in which program effectiveness could be improved. In accordance with the guidance of WHC Management Requirements and Procedures (MRP)5.6, previously identified deficiencies which are being resolved by line management were not repeated as Findings or Observations unless progress or intended disposition was considered to be unsatisfactory

  7. Modern integrated environmental monitoring and processing systems for nuclear facilities

    International Nuclear Information System (INIS)

    Oprea, I.

    2000-01-01

    presentation by using on-line dynamic evolution of the events, environment information, evacuation optimization, image and voice processing. These modern systems are proposed for environmental monitoring around nuclear facilities, as open interactive systems supporting the operator in the global overview of the environment and the status of the situation updating the remote GIS data base, assuring man-computer interaction and a good information flow for emergency knowledge exchange, improving the protection of the population and decision makers efforts. The local monitoring systems could be integrated into national or international environmental monitoring systems, achieving desired interoperability between government, civilian and army in disaster preparedness efforts

  8. Integration of small computers in the low budget facility

    International Nuclear Information System (INIS)

    Miller, G.E.; Crofoot, T.A.

    1988-01-01

    Inexpensive computers (PC's) are well within the reach of low budget reactor facilities. It is possible to envisage many uses that will both improve capabilities of existing instrumentation and also assist operators and staff with certain routine tasks. Both of these opportunities are important for survival at facilities with severe budget and staffing limitations. (author)

  9. Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

    International Nuclear Information System (INIS)

    1985-09-01

    This document, Volume 6 Book 1, contains information on design studies of a Monitored Retrievable Storage (MRS) facility. Topics include materials handling; processing; support systems; support utilities; spent fuel; high-level waste and alpha-bearing waste storage facilities; and field drywell storage

  10. Strategic interaction among hospitals and nursing facilities: the efficiency effects of payment systems and vertical integration.

    Science.gov (United States)

    Banks, D; Parker, E; Wendel, J

    2001-03-01

    Rising post-acute care expenditures for Medicare transfer patients and increasing vertical integration between hospitals and nursing facilities raise questions about the links between payment system structure, the incentive for vertical integration and the impact on efficiency. In the United States, policy-makers are responding to these concerns by initiating prospective payments to nursing facilities, and are exploring the bundling of payments to hospitals. This paper develops a static profit-maximization model of the strategic interaction between the transferring hospital and a receiving nursing facility. This model suggests that the post-1984 system of prospective payment for hospital care, coupled with nursing facility payments that reimburse for services performed, induces inefficient under-provision of hospital services and encourages vertical integration. It further indicates that the extension of prospective payment to nursing facilities will not eliminate the incentive to vertically integrate, and will not result in efficient production unless such integration takes place. Bundling prospective payments for hospitals and nursing facilities will neither remove the incentive for vertical integration nor induce production efficiency without such vertical integration. However, bundled payment will induce efficient production, with or without vertical integration, if nursing facilities are reimbursed for services performed. Copyright 2001 John Wiley & Sons, Ltd.

  11. Monitored retrievable storage (MRS) facility and salt repository integration: Engineering study report

    International Nuclear Information System (INIS)

    1987-07-01

    This MRS Facility and Salt Repository Integration Study evaluates the impacts of an integrated MRS/Salt Repository Waste Management System on the Salt Repository Surface facilities' design, operations, cost, and schedule. Eight separate cases were studied ranging from a two phase repository design with no MRS facility to a design in which the repository only received package waste from the MRS facility for emplacement. The addition of the MRS facility to the Waste Management System significantly reduced the capital cost of the salt repository. All but one of the cases studied were capable of meeting the waste acceptance data. The reduction in the size and complexity of the Salt Repository waste handling building with the integration of the MRS facility reduces the design and operating staff requirements. 7 refs., 35 figs., 43 tabs

  12. Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

    International Nuclear Information System (INIS)

    1985-09-01

    This document, Volume 5 Book 7, contains cost estimate information for a monitored retrievable storage (MRS) facility. Cost estimates are for onsite improvements, waste storage, and offsite improvements for the Clinch River Site

  13. MIMI: Multimodality, Multiresource, Information Integration Environment for Biomedical Core Facilities

    OpenAIRE

    Szymanski, Jacek; Wilson, David L.; Zhang, Guo-Qiang

    2007-01-01

    The rapid expansion of biomedical research has brought substantial scientific and administrative data management challenges to modern core facilities. Scientifically, a core facility must be able to manage experimental workflow and the corresponding set of large and complex scientific data. It must also disseminate experimental data to relevant researchers in a secure and expedient manner that facilitates collaboration and provides support for data interpretation and analysis. Administrativel...

  14. Sugarcane agricultural-industrial facilities and greenhouses integration

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Andres da [Estufas Agricolas Comercio e Assessoria Ltda. (EACEA), SP (Brazil)

    2012-07-01

    This chapter approaches Brazilian greenhouse market and technology, food market trends, integration of bioethanol distilleries with GH production, recovering CO{sub 2} from fermentation process, recovering low temperature energy, using vinasse and bagasse in GH processes, examples of integrated GH in the world, a tomato integrated GH study case, and a business model.

  15. Proposed integrated hazardous waste disposal facility. Public environmental review

    International Nuclear Information System (INIS)

    1998-05-01

    This Public Environmental Report describes a proposal by the Health Department of Western Australia to establish a disposal facility for certain hazardous wastes and seeks comments from governments agencies and the public that will assist the EPA to make its recommendations to. The facility would only be used for wastes generated in Western Australia.The proposal specifically includes: a high temperature incinerator for the disposal of organo-chlorines (including agricultural chemicals and PCBs), and other intractable wastes for which this is the optimum disposal method; an area for the burial (after any appropriate conditioning) of low level radioactive intractable wastes arising from the processing of mineral sands (including monazite, ilmenite and zircon) and phosphate rock. Detailed information is presented on those wastes which are currently identified as requiring disposal at the facility.The proposed facility will also be suitable for the disposal of other intractable wastes including radioactive wastes (from industry, medicine and research) and other solid intractable wastes of a chemical nature including spent catalysts etc. Proposals to dispose of these other wastes at this facility in the future will be referred to the Environmental Protection Authority for separate assessment

  16. CIF---Design basis for an integrated incineration facility

    International Nuclear Information System (INIS)

    Bennett, G.F.

    1991-01-01

    This paper discusses the evolution of chosen technologies that occurred during the design process of the US Department of Energy (DOE) incineration system designated the Consolidated Incineration Facility (CIF) as the Savannah River Plant, Aiken, South Carolina. The Plant is operated for DOE by the Westinghouse Savannah River Company. The purpose of the incineration system is to treat low level radioactive and/or hazardous liquid and solid wastes by combustion. The objective for the facility is to thermally destroy toxic constituents and volume reduce waste material. Design criteria requires operation be controlled within the limits of RCRA's permit envelope

  17. Strategies Used by Facilities in Uganda to Integrate Family Planning ...

    African Journals Online (AJOL)

    Erah

    assistance and coaching from the core team, we integrated routine site/field operations. The performance of each site was monitored using the three FP-HIV care integration indicators – proportion of HIV-positive patients of reproductive age who were: 1) counseled on FP methods at every clinic visit, 2) using at least one FP ...

  18. Improving aircraft accident forecasting for an integrated plutonium storage facility

    International Nuclear Information System (INIS)

    Rock, J.C.; Kiffe, J.; McNerney, M.T.; Turen, T.A.

    1998-06-01

    Aircraft accidents pose a quantifiable threat to facilities used to store and process surplus weapon-grade plutonium. The Department of Energy (DOE) recently published its first aircraft accident analysis guidelines: Accident Analysis for Aircraft Crash into Hazardous Facilities. This document establishes a hierarchy of procedures for estimating the small annual frequency for aircraft accidents that impact Pantex facilities and the even smaller frequency of hazardous material released to the environment. The standard establishes a screening threshold of 10 -6 impacts per year; if the initial estimate of impact frequency for a facility is below this level, no further analysis is required. The Pantex Site-Wide Environmental Impact Statement (SWEIS) calculates the aircraft impact frequency to be above this screening level. The DOE Standard encourages more detailed analyses in such cases. This report presents three refinements, namely, removing retired small military aircraft from the accident rate database, correcting the conversion factor from military accident rates (accidents per 100,000 hours) to the rates used in the DOE model (accidents per flight phase), and adjusting the conditional probability of impact for general aviation to more accurately reflect pilot training and local conditions. This report documents a halving of the predicted frequency of an aircraft impact at Pantex and points toward further reductions

  19. MHD Technology Transfer, Integration and Review Committee. Seventh semi-annual status report, April 1991--September 1991

    Energy Technology Data Exchange (ETDEWEB)

    1993-02-01

    This seventh semi-annual status report of the MHD Technology Transfer, Integration and Review Committee (TTIRC) summarizes activities of the TTIRC during the period April 1991 through September 1991. It includes a summary and minutes of the General Committee meeting, progress summaries of ongoing POC contracts, discussions pertaining to technical integration issues in the POC program, and planned activities for the next six months. The meeting included test plan with Western coal, seed regeneration economics, power management for the integrated topping cycle and status of the Clean Coal Technology Proposal activities. Appendices cover CDIF operations HRSR development, CFFF operations etc.

  20. Performance of simulated flexible integrated gasification polygeneration facilities. Part A: A technical-energetic assessment

    NARCIS (Netherlands)

    Meerman, J.C.; Ramírez Ramírez, C.A.; Turkenburg, W.C.; Faaij, A.P.C.

    2011-01-01

    This article investigates technical possibilities and performances of flexible integrated gasification polygeneration (IG-PG) facilities equipped with CO2 capture for the near future. These facilities can produce electricity during peak hours, while switching to the production of chemicals during

  1. Assessing the economic feasibility of flexible integrated gasification Co-generation facilities

    NARCIS (Netherlands)

    Meerman, J.C.; Ramírez Ramírez, C.A.; Turkenburg, W.C.; Faaij, A.P.C.

    2011-01-01

    This paper evaluated the economic effects of introducing flexibility to state-of-the-art integrated gasification co-generation (IGCG) facilities equipped with CO2 capture. In a previous paper the technical and energetic performances of these flexible IG-CG facilities were evaluated. This paper

  2. Integrating Safeguards into the Pit Disassembly and Conversion Facility

    International Nuclear Information System (INIS)

    Clark, T.G.

    2002-01-01

    In September 2000, the United States and the Russian Federation entered into an agreement which stipulates each country will irreversibly transform 34 metric tons of weapons-grade plutonium into material which could not be used for weapon purposes. Supporting the Department of Energy's (DOE) program to dispose of excess nuclear materials, the Pit Disassembly and Conversion Facility (PDCF) is being designed and constructed to disassemble the weapon ''pits'' and convert the nuclear material to an oxide form for fabrication into reactor fuel at the separate Mixed Oxide Fuel Fabrication Facility. The PDCF design incorporates automation to the maximum extent possible to facilitate material safeguards, reduce worker dose, and improve processing efficiency. This includes provisions for automated guided vehicle movements for shipping containers, material transport via automated conveyor between processes, remote process control monitoring, and automated Nondestructive Assay product systems

  3. Natural circulation in a scaled PWR integral test facility

    International Nuclear Information System (INIS)

    Kiang, R.L.; Jeuck, P.R. III

    1987-01-01

    Natural circulation is an important mechanism for cooling a nuclear power plant under abnormal operating conditions. To study natural circulation, we modeled a type of pressurized water reactor (PWR) that incorporates once-through steam generators. We conducted tests of single-phase natural circulations, two-phase natural circulations, and a boiler condenser mode. Because of complex geometry, the natural circulations observed in this facility exhibit some phenomena not commonly seen in a simple thermosyphon loop

  4. Integrated Human Test Facilities at NASA and the Role of Human Engineering

    Science.gov (United States)

    Tri, Terry O.

    2002-01-01

    Integrated human test facilities are a key component of NASA's Advanced Life Support Program (ALSP). Over the past several years, the ALSP has been developing such facilities to serve as a large-scale advanced life support and habitability test bed capable of supporting long-duration evaluations of integrated bioregenerative life support systems with human test crews. These facilities-targeted for evaluation of hypogravity compatible life support and habitability systems to be developed for use on planetary surfaces-are currently in the development stage at the Johnson Space Center. These major test facilities are comprised of a set of interconnected chambers with a sealed internal environment, which will be outfitted with systems capable of supporting test crews of four individuals for periods exceeding one year. The advanced technology systems to be tested will consist of both biological and physicochemical components and will perform all required crew life support and habitability functions. This presentation provides a description of the proposed test "missions" to be supported by these integrated human test facilities, the overall system architecture of the facilities, the current development status of the facilities, and the role that human design has played in the development of the facilities.

  5. Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

    International Nuclear Information System (INIS)

    1985-09-01

    In April 1985, the Department of Energy (DOE) selected the Clinch River site as its preferred site for the construction and operation of the monitored retrievable storage (MRS) facility (USDOE, 1985). In support of the DOE MRS conceptual design activity, available data describing the site have been gathered and analyzed. A composite geotechnical description of the Clinch River site has been developed and is presented herein. This report presents Clinch River site description data in the following sections: general site description, surface hydrologic characteristics, groundwater characteristics, geologic characteristics, vibratory ground motion, surface faulting, stability of subsurface materials, slope stability, and references. 48 refs., 35 figs., 6 tabs

  6. Systems engineering applied to integrated safety management for high consequence facilities

    International Nuclear Information System (INIS)

    Barter, R; Morais, B.

    1998-01-01

    Integrated Safety Management is a concept that is being actively promoted by the U.S. Department of Energy as a means of assuring safe operation of its facilities. The concept involves the integration of safety precepts into work planning rather than adjusting for safe operations after defining the work activity. The system engineering techniques used to design an integrated safety management system for a high consequence research facility are described. An example is given to show how the concepts evolved with the system design

  7. Simulation of natural circulation on an integral type experimental facility, MASLWR

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Youngjong; Lim, Sungwon; Ha, Jaejoo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-05-15

    The OSU MASLWR test facility was reconfigured to eliminate a recurring grounding problem and improve facility reliability in anticipation of conducting an IAEA International Collaborative Standard Problem (ICSP). The purpose of ICSP is to provide experimental data on flow instability phenomena under natural circulation conditions and coupled containment/reactor vessel behavior in integral-type reactors, and to evaluate system code capabilities to predict natural circulation phenomena for integral type PWR, by simulating an integrated experiment. A natural circulation in the primary side during various core powers is analyzed using TASS/SMR code for the integral type experimental facility. The calculation results show higher steady state primary flow than experiment. If it matches the initial flow with experiment, it shows lower primary flow than experiment according to the increase of power. The code predictions may be improved by applying a Reynolds number dependent form loss coefficient to accurately account for unrecoverable pressure losses.

  8. Bus systems: Integrated facility management; Bus-Systeme: Gewerkeuebergreifende Gebaeudeautomation

    Energy Technology Data Exchange (ETDEWEB)

    Baumgarth, S.; Heiser, M. [Fachhochschule Braunschweig-Wolfenbuettel, Wolfenbuettel (Germany)

    2000-03-01

    Optimisation of facility management relies indispensably on uncomplicated interactive communication between different systems by different producers. An example is described: The system comprises two closed-cycle cooling towers, a cold water set and two different loads (ventilators). Each system can be controlled separately. The trend in automation is in the direction of intelligence even at field level. [German] Unverzichtbare Voraussetzung fuer das Ausschoepfen von Optimierungspotentialen in der Gebaeudeautomation ist die unkomplizierte, wechselseitige Kommunikation zwischen Anlagen und Automatisierungsstationen verschiedener Gewerke und Hersteller. Am Beispiel einer komplexen Anlage, die aus zwei Kuehltuermen mit geschlossenem Kreislauf, einem Kaltwasserersatz sowie unterschiedlichen Verbrauchern (Lueftungsanlagen) besteht, soll die Verknuepfung kaeltetechnischer Gewerke naeher dargestellt werden. Jeder der Teilbereiche ist ueber eine umfangreiche Strategie zu regeln und zu steuern. Dabei geht die Entwicklung in der Gebaeudeautomation hin zu einer Verlagerung der Intelligenz in die Feldebene. (orig./AKF)

  9. Study concerning an integrated radiation monitoring systems for nuclear facilities

    International Nuclear Information System (INIS)

    Oprea, I.; Oprea, M.; Stoica, M.; Cerga, V.; Pirvu, V; Badea, E.

    1996-01-01

    This paper presents an integrated radiation monitoring system designed to assess the effects of nuclear accidents and to provide a basis for making right decisions and countermeasures in order to reduce health damages. The system implies a number of stationary monitoring equipment, data processing unit and a communication network. The system meets the demands of efficiency and reliability, providing the needed tools to easily create programs able to process simple input data filling the information management system. (author). 10 refs

  10. Engineering Task Plan for the Integrity Assessment Examination of Double-Contained Receiver Tanks (DCRT), Catch Tanks and Ancillary facilities

    International Nuclear Information System (INIS)

    BECKER, D.L.

    2000-01-01

    This Engineering Task Plan (ETP) presents the integrity assessment examination of three DCRTs, seven catch tanks, and two ancillary facilities located in the 200 East and West Areas of the Hanford Site. The integrity assessment examinations, as described in this ETP, will provide the necessary information to enable the independently qualified registered professional engineer (IQRPE) to assess the condition and integrity of these facilities. The plan is consistent with the Double-Shell Tank Waste Transfer Facilities Integrity Assessment Plan

  11. Global nuclear material monitoring with NDA and C/S data through integrated facility monitoring

    International Nuclear Information System (INIS)

    Howell, J.A.; Menlove, H.O.; Argo, P.; Goulding, C.; Klosterbuer, S.; Halbig, J.

    1996-01-01

    This paper focuses on a flexible, integrated demonstration of a monitoring approach for nuclear material monitoring. This includes aspects of item signature identification, perimeter portal monitoring, advanced data analysis, and communication as a part of an unattended continuous monitoring system in an operating nuclear facility. Advanced analysis is applied to the integrated nondestructive assay and containment and surveillance data that are synchronized in time. End result will be the foundation for a cost-effective monitoring system that could provide the necessary transparency even in areas that are denied to foreign nationals of both US and Russia should these processes and materials come under full-scope safeguards or bilateral agreements. Monitoring systems of this kind have the potential to provide additional benefits including improved nuclear facility security and safeguards and lower personnel radiation exposures. Demonstration facilities in this paper include VTRAP-prototype, Los Alamos Critical Assemblies Facility, Kazakhstan BM-350 Reactor monitor, DUPIC radiation monitoring, and JOYO and MONJU radiation monitoring

  12. Economic assessment of a proposed integrated resource recovery facility

    International Nuclear Information System (INIS)

    Burnett, J.S.

    1993-01-01

    This report comprises an initial economic and market appraisal of the proposals made by Materials Recycling Management (MRM) Ltd for a commercial plant engaged in waste treatment and energy recovery. The MRM design is an integrated waste handling system for commercial and industrial non hazardous wastes and civic amenity wastes. After primary separation into three selected broad waste categories, wastes are processed in the plant to recover basic recyclables such as paper, timber, plastics and metals. A quantity of material is directed for composting and the remainder converted into a fuel and combusted on site for energy recovery. Wastes unworthy of processing would be sent for disposal. A basic technical review has been undertaken. The focus of this review has been on the main processing plant where materials are segregated and the fuel and compost produced. (author)

  13. Integrated Payment and Delivery Models Offer Opportunities and Challenges for Residential Care Facilities

    OpenAIRE

    Grabowski, David C.; Caudry, Daryl J.; Dean, Katie M.; Stevenson, David G.

    2015-01-01

    Under health care reform, a series of new financing and delivery models are being piloted to integrate health and long-term care services for older adults. To date, these programs have not encompassed residential care facilities, with most programs focusing on long-term care recipients in the community or the nursing home. Our analyses indicate that individuals living in residential care facilities have similarly high rates of chronic illness and Medicare utilization when compared with simila...

  14. The Origin and Constitution of Facilities Management as an integrated corporate fuction

    DEFF Research Database (Denmark)

    Jensen, Per Anker

    2008-01-01

    Purpose – To understand how facilities management (FM) has evolved over time in a complex public corporation from internal functions of building operation and building client and the related service functions to become an integrated corporate function. Design/methodology/approach – The paper...... is based on results from a research project on space strategies and building values, which included a major longitudinal case study of the development of facilities for the Danish Broadcasting Corporation (DR) over time. The research presented here included literature studies, archive studies...... and a fully integrated corporate Facilities Management function are established. Research limitations/implications – The paper presents empirical evidence of the historical development ofFMfrom one case and provides a deeper understanding of the integration processes that are crucial to FM and which can...

  15. Integrated Framework for Patient Safety and Energy Efficiency in Healthcare Facilities Retrofit Projects.

    Science.gov (United States)

    Mohammadpour, Atefeh; Anumba, Chimay J; Messner, John I

    2016-07-01

    There is a growing focus on enhancing energy efficiency in healthcare facilities, many of which are decades old. Since replacement of all aging healthcare facilities is not economically feasible, the retrofitting of these facilities is an appropriate path, which also provides an opportunity to incorporate energy efficiency measures. In undertaking energy efficiency retrofits, it is vital that the safety of the patients in these facilities is maintained or enhanced. However, the interactions between patient safety and energy efficiency have not been adequately addressed to realize the full benefits of retrofitting healthcare facilities. To address this, an innovative integrated framework, the Patient Safety and Energy Efficiency (PATSiE) framework, was developed to simultaneously enhance patient safety and energy efficiency. The framework includes a step -: by -: step procedure for enhancing both patient safety and energy efficiency. It provides a structured overview of the different stages involved in retrofitting healthcare facilities and improves understanding of the intricacies associated with integrating patient safety improvements with energy efficiency enhancements. Evaluation of the PATSiE framework was conducted through focus groups with the key stakeholders in two case study healthcare facilities. The feedback from these stakeholders was generally positive, as they considered the framework useful and applicable to retrofit projects in the healthcare industry. © The Author(s) 2016.

  16. Study of developing nuclear fabrication facility's integrated emergency response manual

    International Nuclear Information System (INIS)

    Kim, Taeh Yeong; Cho, Nam Chan; Han, Seung Hoon; Moon, Jong Han; Lee, Jin Hang; Min, Guem Young; Han, Ji Ah

    2016-01-01

    Public begin to pay attention to emergency management. Thus, public's consensus on having high level of emergency management system up to advanced country's is reached. In this social atmosphere, manual is considered as key factor to prevent accident or secure business continuity. Therefore, we first define possible crisis at KEPCO Nuclear Fuel (hereinafter KNF) and also make a 'Reaction List' for each crisis situation at the view of information-design. To achieve it, we analyze several country's crisis response manual and then derive component, indicate duties and roles at the information-design point of view. From this, we suggested guideline to make 'Integrated emergency response manual(IERM)'. The manual we used before have following few problems; difficult to applicate at the site, difficult to deliver information. To complement these problems, we searched manual elements from the view of information-design. As a result, we develop administrative manual. Although, this manual could be thought as fragmentary manual because it confined specific several agency/organization and disaster type

  17. The Mixed Waste Management Facility. Design basis integrated operations plan (Title I design)

    International Nuclear Information System (INIS)

    1994-12-01

    The Mixed Waste Management Facility (MWMF) will be a fully integrated, pilotscale facility for the demonstration of low-level, organic-matrix mixed waste treatment technologies. It will provide the bridge from bench-scale demonstrated technologies to the deployment and operation of full-scale treatment facilities. The MWMF is a key element in reducing the risk in deployment of effective and environmentally acceptable treatment processes for organic mixed-waste streams. The MWMF will provide the engineering test data, formal evaluation, and operating experience that will be required for these demonstration systems to become accepted by EPA and deployable in waste treatment facilities. The deployment will also demonstrate how to approach the permitting process with the regulatory agencies and how to operate and maintain the processes in a safe manner. This document describes, at a high level, how the facility will be designed and operated to achieve this mission. It frequently refers the reader to additional documentation that provides more detail in specific areas. Effective evaluation of a technology consists of a variety of informal and formal demonstrations involving individual technology systems or subsystems, integrated technology system combinations, or complete integrated treatment trains. Informal demonstrations will typically be used to gather general operating information and to establish a basis for development of formal demonstration plans. Formal demonstrations consist of a specific series of tests that are used to rigorously demonstrate the operation or performance of a specific system configuration

  18. Framework for Integrating Safety, Operations, Security, and Safeguards in the Design and Operation of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Darby, John L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Horak, Karl Emanuel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); LaChance, Jeffrey L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Tolk, Keith Michael [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Whitehead, Donnie Wayne [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2007-10-01

    The US is currently on the brink of a nuclear renaissance that will result in near-term construction of new nuclear power plants. In addition, the Department of Energy’s (DOE) ambitious new Global Nuclear Energy Partnership (GNEP) program includes facilities for reprocessing spent nuclear fuel and reactors for transmuting safeguards material. The use of nuclear power and material has inherent safety, security, and safeguards (SSS) concerns that can impact the operation of the facilities. Recent concern over terrorist attacks and nuclear proliferation led to an increased emphasis on security and safeguard issues as well as the more traditional safety emphasis. To meet both domestic and international requirements, nuclear facilities include specific SSS measures that are identified and evaluated through the use of detailed analysis techniques. In the past, these individual assessments have not been integrated, which led to inefficient and costly design and operational requirements. This report provides a framework for a new paradigm where safety, operations, security, and safeguards (SOSS) are integrated into the design and operation of a new facility to decrease cost and increase effectiveness. Although the focus of this framework is on new nuclear facilities, most of the concepts could be applied to any new, high-risk facility.

  19. Conceptual design of a fission-based integrated test facility for fusion reactor components

    International Nuclear Information System (INIS)

    Watts, K.D.; Deis, G.A.; Hsu, P.Y.S.; Longhurst, G.R.; Masson, L.S.; Miller, L.G.

    1982-01-01

    The testing of fusion materials and components in fission reactors will become increasingly important because of lack of fusion engineering test devices in the immediate future and the increasing long-term demand for fusion testing when a fusion reactor test station becomes available. This paper presents the conceptual design of a fission-based Integrated Test Facility (ITF) developed by EG and G Idaho. This facility can accommodate entire first wall/blanket (FW/B) test modules such as those proposed for INTOR and can also accommodate smaller cylindrical modules similar to those designed by Oak Ridge National laboratory (ORNL) and Westinghouse. In addition, the facility can be used to test bulk breeder blanket materials, materials for tritium permeation, and components for performance in a nuclear environment. The ITF provides a cyclic neutron/gamma flux as well as the numerous module and experiment support functions required for truly integrated tests

  20. Validation of an integral conceptual model of frailty in older residents of assisted living facilities

    NARCIS (Netherlands)

    Gobbens, R.J.J.; Krans, A.; van Assen, M.A.L.M.

    2015-01-01

    Objective The aim of this cross-sectional study was to examine the validity of an integral model of the associations between life-course determinants, disease(s), frailty, and adverse outcomes in older persons who are resident in assisted living facilities. Methods Between June 2013 and May 2014

  1. Validation of an integral conceptual model of frailty in older residents of assisted living facilities

    NARCIS (Netherlands)

    Gobbens, Robbert J J; Krans, Anita; van Assen, Marcel A L M

    2015-01-01

    Objective: The aim of this cross-sectional study was to examine the validity of an integral model of the associations between life-course determinants, disease(s), frailty, and adverse outcomes in older persons who are resident in assisted living facilities. Methods: Between June 2013 and May 2014

  2. The integration of expert knowledge in decision support systems for facility location planning

    NARCIS (Netherlands)

    Arentze, T.A.; Borgers, A.W.J.; Timmermans, H.J.P.

    1995-01-01

    The integration of expert systems in DSS has led to a new generation of systems commonly referred to as knowledge-based or intelligent DSS. This paper investigates the use of expert system technology for the development of a knowledge-based DSS for the planning of retail and service facilities. The

  3. A description of the demonstration Integral Fast Reactor fuel cycle facility

    International Nuclear Information System (INIS)

    Courtney, J.C.; Carnes, M.D.; Dwight, C.C.; Forrester, R.J.

    1991-01-01

    A fuel examination facility at the Idaho National Engineering Laboratory is being converted into a facility that will electrochemically process spent fuel. This is an important step in the demonstration of the Integral Fast Reactor concept being developed by Argonne National Laboratory. Renovations are designed to bring the facility up to current health and safety and environmental standards and to support its new mission. Improvements include the addition of high-reliability earthquake hardened off-gas and electrical power systems, the upgrading of radiological instrumentation, and the incorporation of advances in contamination control. A major task is the construction of a new equipment repair and decontamination facility in the basement of the building to support operations

  4. Integral test facilities for validation of the performance of passive safety systems and natural circulation

    International Nuclear Information System (INIS)

    Choi, J. H.

    2010-10-01

    Passive safety systems are becoming an important component in advanced reactor designs. This has led to an international interest in examining natural circulation phenomena as this may play an important role in the operation of these passive safety systems. Understanding reactor system behaviour is a challenging process due to the complex interactions between components and associated phenomena. Properly scaled integral test facilities can be used to explore these complex interactions. In addition, system analysis computer codes can be used as predictive tools in understanding the complex reactor system behaviour. However, before the application of system analysis computer codes for reactor design, it is capability in making predictions needs to be validated against the experimental data from a properly scaled integral test facility. The IAEA has organized a coordinated research project (CRP) on natural circulation phenomena, modeling and reliability of passive systems that utilize natural circulation. This paper is a part of research results from this CRP and describes representative international integral test facilities that can be used for data collection for reactor types in which natural circulation may play an important role. Example experiments were described along with the analyses of these example cases in order to examine the ability of system codes to model the phenomena that are occurring in the test facilities. (Author)

  5. Integrated Payment And Delivery Models Offer Opportunities And Challenges For Residential Care Facilities.

    Science.gov (United States)

    Grabowski, David C; Caudry, Daryl J; Dean, Katie M; Stevenson, David G

    2015-10-01

    Under health care reform, new financing and delivery models are being piloted to integrate health and long-term care services for older adults. Programs using these models generally have not included residential care facilities. Instead, most of them have focused on long-term care recipients in the community or the nursing home. Our analyses indicate that individuals living in residential care facilities have similarly high rates of chronic illness and Medicare utilization when compared with matched individuals in the community and nursing home, and rates of functional dependency that fall between those of their counterparts in the other two settings. These results suggest that the residential care facility population could benefit greatly from models that coordinated health and long-term care services. However, few providers have invested in the infrastructure needed to support integrated delivery models. Challenges to greater care integration include the private-pay basis for residential care facility services, which precludes shared savings from reduced Medicare costs, and residents' preference for living in a home-like, noninstitutional environment. Project HOPE—The People-to-People Health Foundation, Inc.

  6. Development of an integrated facility for processing transuranium solid wastes at the Savannah River Plant

    International Nuclear Information System (INIS)

    Boersma, M.D.; Hootman, H.E.; Permar, P.H.

    1978-01-01

    An integrated facility is being designed for processing solid wastes contaminated with long-lived alpha emitting (TRU) nuclides; this waste has been stored retrievably at the Savannah River Plant since 1965. The stored waste, having a volume of 10 4 m 3 and containing 3x10 5 Ci of transuranics, consists of both mixed combustible trash and failed and obsolete equipment primarily from transuranic production and associated laboratory operations. The facility for processing solid transuranic waste will consist of five processing modules: 1) unpackaging, sorting, and assaying; 2) treatment of combustibles by controlled air incineration; 3) size reduction of noncombustibles by plasma-arc cutting followed by decontamination by electropolishing; 4) fixation of the processed waste in cement; and 5) packaging for shipment to a federal repository. The facility is projected for construction in the mid-1980's. Pilot facilities, sized to manage currently generated wastes, will also demonstrate the key process steps of incineration of combustibles and size reduction/decontamination of noncombustibles; these facilities are projected for 1980-81. Development programs leading to these extensive new facilities are described

  7. Development of an integrated facility for processing TRU solid wastes at the Savannah River Plant

    International Nuclear Information System (INIS)

    Boersma, M.D.; Hootman, H.E.; Permar, P.H.

    1977-01-01

    An integrated facility is being designed for processing solid wastes contaminated with long-lived alpha emitting (TRU) nuclides; this waste has been stored retrievably at the Savannah River Plant since 1965. The stored waste, having a volume of 10 4 m 3 and containing 3 x 10 5 Ci of transuranics, consists of both mixed combustible trash and failed and obsolete equipment primarily from transuranic production and associated laboratory operations. The facility for processing solid transuranic waste will consist of five processing modules: (1) unpackaging, sorting, and assaying; (2) treatment of combustibles by controlled air incineration; (3) size reduction of noncombustibles by plasma-arc cutting followed by decontamination by electropolishing; (4) fixation of the processed waste in cement; and (5) packaging for shipment to a federal repository. The facility is projected for construction in the mid-1980's. Pilot facilities, sized to manage currently generated wastes, will also demonstrate the key process steps of incineration of combustibles and size reduction/decontamination of noncombustibles; these facilities are projected for 1980-81. Development programs leading to these extensive new facilities are described

  8. Passive BWR integral LOCA testing at the Karlstein test facility INKA

    Energy Technology Data Exchange (ETDEWEB)

    Drescher, Robert [AREVA GmbH, Erlangen (Germany); Wagner, Thomas [AREVA GmbH, Karlstein am Main (Germany); Leyer, Stephan [TH University of Applied Sciences, Deggendorf (Germany)

    2014-05-15

    KERENA is an innovative AREVA GmbH boiling water reactor (BWR) with passive safety systems (Generation III+). In order to verify the functionality of the reactor design an experimental validation program was executed. Therefore the INKA (Integral Teststand Karlstein) test facility was designed and erected. It is a mockup of the BWR containment, with integrated pressure suppression system. While the scaling of the passive components and the levels match the original values, the volume scaling of the containment compartments is approximately 1:24. The storage capacity of the test facility pressure vessel corresponds to approximately 1/6 of the KERENA RPV and is supplied by a benson boiler with a thermal power of 22 MW. In March 2013 the first integral test - Main Steam Line Break (MSLB) - was executed. The test measured the combined response of the passive safety systems to the postulated initiating event. The main goal was to demonstrate the ability of the passive systems to ensure core coverage, decay heat removal and to maintain the containment within defined limits. The results of the test showed that the passive safety systems are capable to bring the plant to stable conditions meeting all required safety targets with sufficient margins. Therefore the test verified the function of those components and the interplay between them. The test proved that INKA is an unique test facility, capable to perform integral tests of passive safety concepts under plant-like conditions. (orig.)

  9. Supporting Facility Management Processes through End-Users’ Integration and Coordinated BIM-GIS Technologies

    Directory of Open Access Journals (Sweden)

    Claudio Mirarchi

    2018-05-01

    Full Text Available The integration of facility management and building information modelling (BIM is an innovative and critical undertaking process to support facility maintenance and management. Even though recent research has proposed various methods and performed an increasing number of case studies, there are still issues of communication processes to be addressed. This paper presents a theoretical framework for digital systems integration of virtual models and smart technologies. Based on the comprehensive analysis of existing technologies for indoor localization, a new workflow is defined and designed, and it is utilized in a practical case study to test the model performance. In the new workflow, a facility management supporting platform is proposed and characterized, featuring indoor positioning systems to allow end users to send geo-referenced reports to central virtual models. In addition, system requirements, information technology (IT architecture and application procedures are presented. Results show that the integration of end users in the maintenance processes through smart and easy tools can overcome the existing limits of barcode systems and building management systems for failure localization. The proposed framework offers several advantages. First, it allows the identification of every element of an asset including wide physical building elements (walls, floors, etc. without requiring a prior mapping. Second, the entire cycle of maintenance activities is managed through a unique integrated system including the territorial dimension. Third, data are collected in a standard structure for future uses. Furthermore, the integration of the process in a centralized BIM-GIS (geographical information system information management system admit a scalable representation of the information supporting facility management processes in terms of assets and supply chain management and monitoring from a spatial perspective.

  10. Structural integrity assessment based on the HFR Petten neutron beam facilities

    CERN Document Server

    Ohms, C; Idsert, P V D

    2002-01-01

    Neutrons are becoming recognized as a valuable tool for structural-integrity assessment of industrial components and advanced materials development. Microstructure, texture and residual stress analyses are commonly performed by neutron diffraction and a joint CEN/ISO Pre-Standard for residual stress analysis is under development. Furthermore neutrons provide for defects analyses, i.e. precipitations, voids, pores and cracks, through small-angle neutron scattering (SANS) or radiography. At the High Flux Reactor, 12 beam tubes have been installed for the extraction of thermal neutrons for such applications. Two of them are equipped with neutron diffractometers for residual stress and structure determination and have been extensively used in the past. Several other facilities are currently being reactivated and upgraded. These include the SANS and radiography facilities as well as a powder diffractometer. This paper summarizes the main characteristics and current status of these facilities as well as recently in...

  11. Introduction to Large-sized Test Facility for validating Containment Integrity under Severe Accidents

    International Nuclear Information System (INIS)

    Na, Young Su; Hong, Seongwan; Hong, Seongho; Min, Beongtae

    2014-01-01

    An overall assessment of containment integrity can be conducted properly by examining the hydrogen behavior in the containment building. Under severe accidents, an amount of hydrogen gases can be generated by metal oxidation and corium-concrete interaction. Hydrogen behavior in the containment building strongly depends on complicated thermal hydraulic conditions with mixed gases and steam. The performance of a PAR can be directly affected by the thermal hydraulic conditions, steam contents, gas mixture behavior and aerosol characteristics, as well as the operation of other engineering safety systems such as a spray. The models in computer codes for a severe accident assessment can be validated based on the experiment results in a large-sized test facility. The Korea Atomic Energy Research Institute (KAERI) is now preparing a large-sized test facility to examine in detail the safety issues related with hydrogen including the performance of safety devices such as a PAR in various severe accident situations. This paper introduces the KAERI test facility for validating the containment integrity under severe accidents. To validate the containment integrity, a large-sized test facility is necessary for simulating complicated phenomena induced by an amount of steam and gases, especially hydrogen released into the containment building under severe accidents. A pressure vessel 9.5 m in height and 3.4 m in diameter was designed at the KAERI test facility for the validating containment integrity, which was based on the THAI test facility with the experimental safety and the reliable measurement systems certified for a long time. This large-sized pressure vessel operated in steam and iodine as a corrosive agent was made by stainless steel 316L because of corrosion resistance for a long operating time, and a vessel was installed in at KAERI in March 2014. In the future, the control systems for temperature and pressure in a vessel will be constructed, and the measurement system

  12. Validation of an integral conceptual model of frailty in older residents of assisted living facilities.

    Science.gov (United States)

    Gobbens, Robbert J J; Krans, Anita; van Assen, Marcel A L M

    2015-01-01

    The aim of this cross-sectional study was to examine the validity of an integral model of the associations between life-course determinants, disease(s), frailty, and adverse outcomes in older persons who are resident in assisted living facilities. Between June 2013 and May 2014 seven assisted living facilities were contacted. A total of 221 persons completed the questionnaire on life-course determinants, frailty (using the Tilburg Frailty Indicator), self-reported chronic diseases, and adverse outcomes disability, quality of life, health care utilization, and falls. Adverse outcomes were analyzed with sequential (logistic) regression analyses. The integral model is partially validated. Life-course determinants and disease(s) affected only physical frailty. All three frailty domains (physical, psychological, social) together affected disability, quality of life, visits to a general practitioner, and falls. Contrary to the model, disease(s) had no effect on adverse outcomes after controlling for frailty. Life-course determinants affected adverse outcomes, with unhealthy lifestyle having consistent negative effects, and women had more disability, scored lower on physical health, and received more personal and informal care after controlling for all other predictors. The integral model of frailty is less useful for predicting adverse outcomes of residents of assisted living facilities than for community-dwelling older persons, because these residents are much frailer and already have access to healthcare facilities. The present study showed that a multidimensional assessment of frailty, distinguishing three domains of frailty (physical, psychological, social), is beneficial with respect to predicting adverse outcomes in residents of assisted living facilities. Copyright © 2015. Published by Elsevier Ireland Ltd.

  13. An integrated prediction and optimization model of biogas production system at a wastewater treatment facility.

    Science.gov (United States)

    Akbaş, Halil; Bilgen, Bilge; Turhan, Aykut Melih

    2015-11-01

    This study proposes an integrated prediction and optimization model by using multi-layer perceptron neural network and particle swarm optimization techniques. Three different objective functions are formulated. The first one is the maximization of methane percentage with single output. The second one is the maximization of biogas production with single output. The last one is the maximization of biogas quality and biogas production with two outputs. Methane percentage, carbon dioxide percentage, and other contents' percentage are used as the biogas quality criteria. Based on the formulated models and data from a wastewater treatment facility, optimal values of input variables and their corresponding maximum output values are found out for each model. It is expected that the application of the integrated prediction and optimization models increases the biogas production and biogas quality, and contributes to the quantity of electricity production at the wastewater treatment facility. Copyright © 2015 Elsevier Ltd. All rights reserved.

  14. Track Reconstruction with Cosmic Ray Data at the Tracker Integration Facility

    CERN Document Server

    Adam, Wolfgang; Dragicevic, Marko; Friedl, Markus; Fruhwirth, R; Hansel, S; Hrubec, Josef; Krammer, Manfred; Oberegger, Margit; Pernicka, Manfred; Schmid, Siegfried; Stark, Roland; Steininger, Helmut; Uhl, Dieter; Waltenberger, Wolfgang; Widl, Edmund; Van Mechelen, Pierre; Cardaci, Marco; Beaumont, Willem; de Langhe, Eric; de Wolf, Eddi A; Delmeire, Evelyne; Hashemi, Majid; Bouhali, Othmane; Charaf, Otman; Clerbaux, Barbara; Elgammal, J.-P. Dewulf. S; Hammad, Gregory Habib; de Lentdecker, Gilles; Marage, Pierre Edouard; Vander Velde, Catherine; Vanlaer, Pascal; Wickens, John; Adler, Volker; Devroede, Olivier; De Weirdt, Stijn; D'Hondt, Jorgen; Goorens, Robert; Heyninck, Jan; Maes, Joris; Mozer, Matthias Ulrich; Tavernier, Stefaan; Van Lancker, Luc; Van Mulders, Petra; Villella, Ilaria; Wastiels, C; Bonnet, Jean-Luc; Bruno, Giacomo; De Callatay, Bernard; Florins, Benoit; Giammanco, Andrea; Gregoire, Ghislain; Keutgen, Thomas; Kcira, Dorian; Lemaitre, Vincent; Michotte, Daniel; Militaru, Otilia; Piotrzkowski, Krzysztof; Quertermont, L; Roberfroid, Vincent; Rouby, Xavier; Teyssier, Daniel; Daubie, Evelyne; Anttila, Erkki; Czellar, Sandor; Engstrom, Pauli; Harkonen, J; Karimaki, V; Kostesmaa, J; Kuronen, Auli; Lampen, Tapio; Linden, Tomas; Luukka, Panja-Riina; Maenpaa, T; Michal, Sebastien; Tuominen, Eija; Tuominiemi, Jorma; Ageron, Michel; Baulieu, Guillaume; Bonnevaux, Alain; Boudoul, Gaelle; Chabanat, Eric; Chabert, Eric Christian; Chierici, Roberto; Contardo, Didier; Della Negra, Rodolphe; Dupasquier, Thierry; Gelin, Georges; Giraud, Noël; Guillot, Gérard; Estre, Nicolas; Haroutunian, Roger; Lumb, Nicholas; Perries, Stephane; Schirra, Florent; Trocme, Benjamin; Vanzetto, Sylvain; Agram, Jean-Laurent; Blaes, Reiner; Drouhin, Frédéric; Ernenwein, Jean-Pierre; Fontaine, Jean-Charles; Berst, Jean-Daniel; Brom, Jean-Marie; Didierjean, Francois; Goerlach, Ulrich; Graehling, Philippe; Gross, Laurent; Hosselet, J; Juillot, Pierre; Lounis, Abdenour; Maazouzi, Chaker; Olivetto, Christian; Strub, Roger; Van Hove, Pierre; Anagnostou, Georgios; Brauer, Richard; Esser, Hans; Feld, Lutz; Karpinski, Waclaw; Klein, Katja; Kukulies, Christoph; Olzem, Jan; Ostapchuk, Andrey; Pandoulas, Demetrios; Pierschel, Gerhard; Raupach, Frank; Schael, Stefan; Schwering, Georg; Sprenger, Daniel; Thomas, Maarten; Weber, Markus; Wittmer, Bruno; Wlochal, Michael; Beissel, Franz; Bock, E; Flugge, G; Gillissen, C; Hermanns, Thomas; Heydhausen, Dirk; Jahn, Dieter; Kaussen, Gordon; Linn, Alexander; Perchalla, Lars; Poettgens, Michael; Pooth, Oliver; Stahl, Achim; Zoeller, Marc Henning; Buhmann, Peter; Butz, Erik; Flucke, Gero; Hamdorf, Richard Helmut; Hauk, Johannes; Klanner, Robert; Pein, Uwe; Schleper, Peter; Steinbruck, G; Blum, P; De Boer, Wim; Dierlamm, Alexander; Dirkes, Guido; Fahrer, Manuel; Frey, Martin; Furgeri, Alexander; Hartmann, Frank; Heier, Stefan; Hoffmann, Karl-Heinz; Kaminski, Jochen; Ledermann, Bernhard; Liamsuwan, Thiansin; Muller, S; Muller, Th; Schilling, Frank-Peter; Simonis, Hans-Jürgen; Steck, Pia; Zhukov, Valery; Cariola, P; De Robertis, Giuseppe; Ferorelli, Raffaele; Fiore, Luigi; Preda, M; Sala, Giuliano; Silvestris, Lucia; Tempesta, Paolo; Zito, Giuseppe; Creanza, Donato; De Filippis, Nicola; De Palma, Mauro; Giordano, Domenico; Maggi, Giorgio; Manna, Norman; My, Salvatore; Selvaggi, Giovanna; Albergo, Sebastiano; Chiorboli, Massimiliano; Costa, Salvatore; Galanti, Mario; Giudice, Nunzio; Guardone, Nunzio; Noto, Francesco; Potenza, Renato; Saizu, Mirela Angela; Sparti, V; Sutera, Concetta; Tricomi, Alessia; Tuve, Cristina; Brianzi, Mirko; Civinini, Carlo; Maletta, Fernando; Manolescu, Florentina; Meschini, Marco; Paoletti, Simone; Sguazzoni, Giacomo; Broccolo, B; Ciulli, Vitaliano; Focardi, R. D'Alessandro. E; Frosali, Simone; Genta, Chiara; Landi, Gregorio; Lenzi, Piergiulio; Macchiolo, Anna; Magini, Nicolo; Parrini, Giuliano; Scarlini, Enrico; Cerati, Giuseppe Benedetto; Azzi, Patrizia; Bacchetta, Nicola; Candelori, Andrea; Dorigo, Tommaso; Kaminsky, A; Karaevski, S; Khomenkov, Volodymyr; Reznikov, Sergey; Tessaro, Mario; Bisello, Dario; De Mattia, Marco; Giubilato, Piero; Loreti, Maurizio; Mattiazzo, Serena; Nigro, Massimo; Paccagnella, Alessandro; Pantano, Devis; Pozzobon, Nicola; Tosi, Mia; Bilei, Gian Mario; Checcucci, Bruno; Fano, Livio; Servoli, Leonello; Ambroglini, Filippo; Babucci, Ezio; Benedetti, Daniele; Biasini, Maurizio; Caponeri, Benedetta; Covarelli, Roberto; Giorgi, Marco; Lariccia, Paolo; Mantovani, Giancarlo; Marcantonini, Marta; Postolache, Vasile; Santocchia, Attilio; Spiga, Daniele; Bagliesi, Giuseppe; Balestri, Gabriele; Berretta, Luca; Bianucci, S; Boccali, Tommaso; Bosi, Filippo; Bracci, Fabrizio; Castaldi, Rino; Ceccanti, Marco; Cecchi, Roberto; Cerri, Claudio; Cucoanes, Andi Sebastian; Dell'Orso, Roberto; Dobur, Didar; Dutta, Suchandra; Giassi, Alessandro; Giusti, Simone; Kartashov, Dmitry; Kraan, Aafke; Lomtadze, Teimuraz; Lungu, George-Adrian; Magazzu, Guido; Mammini, Paolo; Mariani, Filippo; Martinelli, Giovanni; Moggi, Andrea; Palla, Fabrizio; Palmonari, Francesco; Petragnani, Giulio; Profeti, Alessandro; Raffaelli, Fabrizio; Rizzi, Domenico; Sanguinetti, Giulio; Sarkar, Subir; Sentenac, Daniel; Serban, Alin Titus; Slav, Adrian; Soldani, A; Spagnolo, Paolo; Tenchini, Roberto; Tolaini, Sergio; Venturi, Andrea; Verdini, Piero Giorgio; Vos, Marcel; Zaccarelli, Luciano; Avanzini, Carlo; Basti, Andrea; Benucci, Leonardo; Bocci, Andrea; Cazzola, Ugo; Fiori, Francesco; Linari, Stefano; Massa, Maurizio; Messineo, Alberto; Segneri, Gabriele; Tonelli, Guido; Azzurri, Paolo; Bernardini, Jacopo; Borrello, Laura; Calzolari, Federico; Foa, Lorenzo; Gennai, Simone; Ligabue, Franco; Petrucciani, Giovanni; Rizzi, Andrea; Yang, Zong-Chang; Benotto, Franco; Demaria, Natale; Dumitrache, Floarea; Farano, R; Borgia, Maria Assunta; Castello, Roberto; Costa, Marco; Migliore, Ernesto; Romero, Alessandra; Abbaneo, Duccio; Abbas, M; Ahmed, Ijaz; Akhtar, I; Albert, Eric; Bloch, Christoph; Breuker, Horst; Butt, Shahid Aleem; Buchmuller, Oliver; Cattai, Ariella; Delaere, Christophe; Delattre, Michel; Edera, Laura Maria; Engstrom, Pauli; Eppard, Michael; Gateau, Maryline; Gill, Karl; Giolo-Nicollerat, Anne-Sylvie; Grabit, Robert; Honma, Alan; Huhtinen, Mika; Kloukinas, Kostas; Kortesmaa, Jarmo; Kottelat, Luc-Joseph; Kuronen, Auli; Leonardo, Nuno; Ljuslin, Christer; Mannelli, Marcello; Masetti, Lorenzo; Marchioro, Alessandro; Mersi, Stefano; Michal, Sebastien; Mirabito, Laurent; Muffat-Joly, Jeannine; Onnela, Antti; Paillard, Christian; Pal, Imre; Pernot, Jean-Francois; Petagna, Paolo; Petit, Patrick; Piccut, C; Pioppi, Michele; Postema, Hans; Ranieri, Riccardo; Ricci, Daniel; Rolandi, Gigi; Ronga, Frederic Jean; Sigaud, Christophe; Syed, A; Siegrist, Patrice; Tropea, Paola; Troska, Jan; Tsirou, Andromachi; Vander Donckt, Muriel; Vasey, François; Alagoz, Enver; Amsler, Claude; Chiochia, Vincenzo; Regenfus, Christian; Robmann, Peter; Rochet, Jacky; Rommerskirchen, Tanja; Schmidt, Alexander; Steiner, Stefan; Wilke, Lotte; Church, Ivan; Cole, Joanne; Coughlan, John A; Gay, Arnaud; Taghavi, S; Tomalin, Ian R; Bainbridge, Robert; Cripps, Nicholas; Fulcher, Jonathan; Hall, Geoffrey; Noy, Matthew; Pesaresi, Mark; Radicci, Valeria; Raymond, David Mark; Sharp, Peter; Stoye, Markus; Wingham, Matthew; Zorba, Osman; Goitom, Israel; Hobson, Peter R; Reid, Ivan; Teodorescu, Liliana; Hanson, Gail; Jeng, Geng-Yuan; Liu, Haidong; Pasztor, Gabriella; Satpathy, Asish; Stringer, Robert; Mangano, Boris; Affolder, K; Affolder, T; Allen, Andrea; Barge, Derek; Burke, Samuel; Callahan, D; Campagnari, Claudio; Crook, A; D'Alfonso, Mariarosaria; Dietch, J; Garberson, Jeffrey; Hale, David; Incandela, H; Incandela, Joe; Jaditz, Stephen; Kalavase, Puneeth; Kreyer, Steven Lawrence; Kyre, Susanne; Lamb, James; Mc Guinness, C; Mills, C; Nguyen, Harold; Nikolic, Milan; Lowette, Steven; Rebassoo, Finn; Ribnik, Jacob; Richman, Jeffrey; Rubinstein, Noah; Sanhueza, S; Shah, Yousaf Syed; Simms, L; Staszak, D; Stoner, J; Stuart, David; Swain, Sanjay Kumar; Vlimant, Jean-Roch; White, Dean; Ulmer, Keith; Wagner, Stephen Robert; Bagby, Linda; Bhat, Pushpalatha C; Burkett, Kevin; Cihangir, Selcuk; Gutsche, Oliver; Jensen, Hans; Johnson, Mark; Luzhetskiy, Nikolay; Mason, David; Miao, Ting; Moccia, Stefano; Noeding, Carsten; Ronzhin, Anatoly; Skup, Ewa; Spalding, William J; Spiegel, Leonard; Tkaczyk, Slawek; Yumiceva, Francisco; Zatserklyaniy, Andriy; Zerev, E; Anghel, Ioana Maria; Bazterra, Victor Eduardo; Gerber, Cecilia Elena; Khalatian, S; Shabalina, Elizaveta; Baringer, Philip; Bean, Alice; Chen, Jie; Hinchey, Carl Louis; Martin, Christophe; Moulik, Tania; Robinson, Richard; Gritsan, Andrei; Lae, Chung Khim; Tran, Nhan Viet; Everaerts, Pieter; Hahn, Kristan Allan; Harris, Philip; Nahn, Steve; Rudolph, Matthew; Sung, Kevin; Betchart, Burton; Demina, Regina; Gotra, Yury; Korjenevski, Sergey; Miner, Daniel Carl; Orbaker, Douglas; Christofek, Leonard; Hooper, Ryan; Landsberg, Greg; Nguyen, Duong; Narain, Meenakshi; Speer, Thomas; Tsang, Ka Vang

    2008-01-01

    The subsystems of the CMS silicon strip tracker were integrated and commissioned at the Tracker Integration Facility (TIF) in the period from November 2006 to July 2007. As part of the commissioning, large samples of cosmic ray data were recorded under various running conditions in the absence of a magnetic field. Cosmic rays detected by scintillation counters were used to trigger the readout of up to 15\\,\\% of the final silicon strip detector, and over 4.7~million events were recorded. This document describes the cosmic track reconstruction and presents results on the performance of track and hit reconstruction as from dedicated analyses.

  15. An Integrated Assessment of Location-Dependent Scaling for Microalgae Biofuel Production Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Coleman, Andre M.; Abodeely, Jared; Skaggs, Richard; Moeglein, William AM; Newby, Deborah T.; Venteris, Erik R.; Wigmosta, Mark S.

    2014-06-19

    Successful development of a large-scale microalgae-based biofuels industry requires comprehensive analysis and understanding of the feedstock supply chain—from facility siting/design through processing/upgrading of the feedstock to a fuel product. The evolution from pilot-scale production facilities to energy-scale operations presents many multi-disciplinary challenges, including a sustainable supply of water and nutrients, operational and infrastructure logistics, and economic competitiveness with petroleum-based fuels. These challenges are addressed in part by applying the Integrated Assessment Framework (IAF)—an integrated multi-scale modeling, analysis, and data management suite—to address key issues in developing and operating an open-pond facility by analyzing how variability and uncertainty in space and time affect algal feedstock production rates, and determining the site-specific “optimum” facility scale to minimize capital and operational expenses. This approach explicitly and systematically assesses the interdependence of biofuel production potential, associated resource requirements, and production system design trade-offs. The IAF was applied to a set of sites previously identified as having the potential to cumulatively produce 5 billion-gallons/year in the southeastern U.S. and results indicate costs can be reduced by selecting the most effective processing technology pathway and scaling downstream processing capabilities to fit site-specific growing conditions, available resources, and algal strains.

  16. Integrated leak rate test of the FFTF [Fast Flux Test Facility] containment vessel

    International Nuclear Information System (INIS)

    Grygiel, M.L.; Davis, R.H.; Polzin, D.L.; Yule, W.D.

    1987-04-01

    The third integrated leak rate test (ILRT) performed at the Fast Flux Test Facility (FFTF) demonstrated that effective leak rate measurements could be obtained at a pressure of 2 psig. In addition, innovative data reduction methods demonstrated the ability to accurately account for diurnal variations in containment pressure and temperature. Further development of methods used in this test indicate significant savings in the time and effort required to perform an ILRT on Liquid Metal Reactor Systems with consequent reduction in test costs

  17. Development of Integral Effect Test Facility P and ID and Technical Specification for SMART Fluid System

    International Nuclear Information System (INIS)

    Lee, Sang Il; Jung, Y. H.; Yang, H. J.; Song, S. Y.; Han, O. J.; Lee, B. J.; Kim, Y. A.; Lim, J. H.; Park, K. W.; Kim, N. G.

    2010-01-01

    SMART integral test loop is the thermal hydraulic test facility with a high pressure and temperature for simulating the major systems of the prototype reactor, SMART-330. The objective of this project is to conduct the basic design for constructing SMART ITL. The major results of this project include a series of design documents, technical specifications and P and ID. The results can be used as the fundamental materials for making the detailed design which is essential for manufacturing and installing SMART ITL

  18. Integration of the SSPM and STAGE with the MPACT Virtual Facility Distributed Test Bed.

    Energy Technology Data Exchange (ETDEWEB)

    Cipiti, Benjamin B. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Shoman, Nathan [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-08-01

    The Material Protection Accounting and Control Technologies (MPACT) program within DOE NE is working toward a 2020 milestone to demonstrate a Virtual Facility Distributed Test Bed. The goal of the Virtual Test Bed is to link all MPACT modeling tools, technology development, and experimental work to create a Safeguards and Security by Design capability for fuel cycle facilities. The Separation and Safeguards Performance Model (SSPM) forms the core safeguards analysis tool, and the Scenario Toolkit and Generation Environment (STAGE) code forms the core physical security tool. These models are used to design and analyze safeguards and security systems and generate performance metrics. Work over the past year has focused on how these models will integrate with the other capabilities in the MPACT program and specific model changes to enable more streamlined integration in the future. This report describes the model changes and plans for how the models will be used more collaboratively. The Virtual Facility is not designed to integrate all capabilities into one master code, but rather to maintain stand-alone capabilities that communicate results between codes more effectively.

  19. Integrated Electrical and Thermal Grid Facility - Testing of Future Microgrid Technologies

    Directory of Open Access Journals (Sweden)

    Sundar Raj Thangavelu

    2015-09-01

    Full Text Available This paper describes the Experimental Power Grid Centre (EPGC microgrid test facility, which was developed to enable research, development and testing for a wide range of distributed generation and microgrid technologies. The EPGC microgrid facility comprises a integrated electrical and thermal grid with a flexible and configurable architecture, and includes various distributed energy resources and emulators, such as generators, renewable, energy storage technologies and programmable load banks. The integrated thermal grid provides an opportunity to harness waste heat produced by the generators for combined heat, power and cooling applications, and support research in optimization of combined electrical-thermal systems. Several case studies are presented to demonstrate the testing of different control and operation strategies for storage systems in grid-connected and islanded microgrids. One of the case studies also demonstrates an integrated thermal grid to convert waste heat to useful energy, which thus far resulted in a higher combined energy efficiency. Experiment results confirm that the facility enables testing and evaluation of grid technologies and practical problems that may not be apparent in a computer simulated environment.

  20. Long term integrity of spent fuel and construction materials for dry storage facilities

    Energy Technology Data Exchange (ETDEWEB)

    Saegusa, T [CRIEPI (Japan)

    2012-07-01

    In Japan, two dry storage facilities at reactor sites have already been operating since 1995 and 2002, respectively. Additionally, a large scale dry storage facility away from reactor sites is under safety examination for license near the coast and desired to start its operation in 2010. Its final storage capacity is 5,000tU. It is therefore necessary to obtain and evaluate the related data on integrity of spent fuels loaded into and construction materials of casks during long term dry storage. The objectives are: - Spent fuel rod: To evaluate hydrogen migration along axial fuel direction on irradiated claddings stored for twenty years in air; To evaluate pellet oxidation behaviour for high burn-up UO{sub 2} fuels; - Construction materials for dry storage facilities: To evaluate long term reliability of welded stainless steel canister under stress corrosion cracking (SCC) environment; To evaluate long term integrity of concrete cask under carbonation and salt attack environment; To evaluate integrity of sealability of metal gasket under long term storage and short term accidental impact force.

  1. Integrated operations plan for the MFTF-B Mirror Fusion Test Facility. Volume II. Integrated operations plan

    Energy Technology Data Exchange (ETDEWEB)

    1981-12-01

    This document defines an integrated plan for the operation of the Lawrence Livermore National Laboratory (LLNL) Mirror Fusion Test Facility (MFTF-B). The plan fulfills and further delineates LLNL policies and provides for accomplishing the functions required by the program. This plan specifies the management, operations, maintenance, and engineering support responsibilities. It covers phasing into sustained operations as well as the sustained operations themselves. Administrative and Plant Engineering support, which are now being performed satisfactorily, are not part of this plan unless there are unique needs.

  2. Integrated operations plan for the MFTF-B Mirror Fusion Test Facility. Volume II. Integrated operations plan

    International Nuclear Information System (INIS)

    1981-12-01

    This document defines an integrated plan for the operation of the Lawrence Livermore National Laboratory (LLNL) Mirror Fusion Test Facility (MFTF-B). The plan fulfills and further delineates LLNL policies and provides for accomplishing the functions required by the program. This plan specifies the management, operations, maintenance, and engineering support responsibilities. It covers phasing into sustained operations as well as the sustained operations themselves. Administrative and Plant Engineering support, which are now being performed satisfactorily, are not part of this plan unless there are unique needs

  3. Adequacy of power-to-volume scaling philosophy to simulate natural circulation in Integral Test Facilities

    International Nuclear Information System (INIS)

    Nayak, A.K.; Vijayan, P.K.; Saha, D.; Venkat Raj, V.; Aritomi, Masanori

    1998-01-01

    Theoretical and experimental investigations were carried out to study the adequacy of power-to-volume scaling philosophy for the simulation of natural circulation and to establish the scaling philosophy applicable for the design of the Integral Test Facility (ITF-AHWR) for the Indian Advanced Heavy Water Reactor (AHWR). The results indicate that a reduction in the flow channel diameter of the scaled facility as required by the power-to-volume scaling philosophy may affect the simulation of natural circulation behaviour of the prototype plants. This is caused by the distortions due to the inability to simulate the frictional resistance of the scaled facility. Hence, it is recommended that the flow channel diameter of the scaled facility should be as close as possible to the prototype. This was verified by comparing the natural circulation behaviour of a prototype 220 MWe Indian PHWR and its scaled facility (FISBE-1) designed based on power-to-volume scaling philosophy. It is suggested from examinations using a mathematical model and a computer code that the FISBE-1 simulates the steady state and the general trend of transient natural circulation behaviour of the prototype reactor adequately. Finally the proposed scaling method was applied for the design of the ITF-AHWR. (author)

  4. CMT scaling analysis and distortion evaluation in passive integral test facility

    International Nuclear Information System (INIS)

    Deng Chengcheng; Qin Benke; Wang Han; Chang Huajian

    2013-01-01

    Core makeup tank (CMT) is the crucial device of AP1000 passive core cooling system, and reasonable scaling analysis of CMT plays a key role in the design of passive integral test facilities. H2TS method was used to perform scaling analysis for both circulating mode and draining mode of CMT. And then, the similarity criteria for CMT important processes were applied in the CMT scaling design of the ACME (advanced core-cooling mechanism experiment) facility now being built in China. Furthermore, the scaling distortion results of CMT characteristic Ⅱ groups of ACME were calculated. At last, the reason of scaling distortion was analyzed and the distortion evaluation was conducted for ACME facility. The dominant processes of CMT circulating mode can be adequately simulated in the ACME facility, but the steam condensation process during CMT draining is not well preserved because the excessive CMT mass leads to more energy to be absorbed by cold metal. However, comprehensive analysis indicates that the ACME facility with high-pressure simulation scheme is able to properly represent CMT's important phenomena and processes of prototype nuclear plant. (authors)

  5. CPP-603 Underwater Fuel Storage Facility Site Integrated Stabilization Management Plan (SISMP), Volume I

    International Nuclear Information System (INIS)

    Denney, R.D.

    1995-10-01

    The CPP-603 Underwater Fuel Storage Facility (UFSF) Site Integrated Stabilization Management Plan (SISMP) has been constructed to describe the activities required for the relocation of spent nuclear fuel (SNF) from the CPP-603 facility. These activities are the only Idaho National Engineering Laboratory (INEL) actions identified in the Implementation Plan developed to meet the requirements of the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1 to the Secretary of Energy regarding an improved schedule for remediation in the Defense Nuclear Facilities Complex. As described in the DNFSB Recommendation 94-1 Implementation Plan, issued February 28, 1995, an INEL Spent Nuclear Fuel Management Plan is currently under development to direct the placement of SNF currently in existing INEL facilities into interim storage, and to address the coordination of intrasite SNF movements with new receipts and intersite transfers that were identified in the DOE SNF Programmatic and INEL Environmental Restoration and Waste Management Environmental Impact Statement Record, of Decision. This SISMP will be a subset of the INEL Spent Nuclear Fuel Management Plan and the activities described are being coordinated with other INEL SNF management activities. The CPP-603 relocation activities have been assigned a high priority so that established milestones will be meet, but there will be some cases where other activities will take precedence in utilization of available resources. The Draft INEL Site Integrated Stabilization Management Plan (SISMP), INEL-94/0279, Draft Rev. 2, dated March 10, 1995, is being superseded by the INEL Spent Nuclear Fuel Management Plan and this CPP-603 specific SISMP

  6. Integration of distributed plant process computer systems to nuclear power generation facilities

    International Nuclear Information System (INIS)

    Bogard, T.; Finlay, K.

    1996-01-01

    Many operating nuclear power generation facilities are replacing their plant process computer. Such replacement projects are driven by equipment obsolescence issues and associated objectives to improve plant operability, increase plant information access, improve man machine interface characteristics, and reduce operation and maintenance costs. This paper describes a few recently completed and on-going replacement projects with emphasis upon the application integrated distributed plant process computer systems. By presenting a few recent projects, the variations of distributed systems design show how various configurations can address needs for flexibility, open architecture, and integration of technological advancements in instrumentation and control technology. Architectural considerations for optimal integration of the plant process computer and plant process instrumentation ampersand control are evident from variations of design features

  7. A Study of Critical Flowrate in the Integral Effect Test Facilities

    International Nuclear Information System (INIS)

    Kim, Yeongsik; Ryu, Sunguk; Cho, Seok; Yi, Sungjae; Park, Hyunsik

    2014-01-01

    In earlier studies, most of the information available in the literature was either for a saturated two-phase flow or a sub-cooled water flow at medium pressure conditions, e. g., up to about 7.0 MPa. The choking is regarded as a condition of maximum possible discharge through a given orifice and/or nozzle exit area. A critical flow rate can be achieved at a choking under the given thermo-hydraulic conditions. The critical flow phenomena were studied extensively in both single-phase and two-phase systems because of its importance in the LOCA analyses of light water reactors and in the design of other engineering areas. Park suggested a modified correlation for predicting the critical flow for sub-cooled water through a nozzle. Recently, Park et al. performed an experimental study on a two-phase critical flow with a noncondensable gas at high pressure conditions. Various experiments of critical flow using sub-cooled water were performed for a modeling of break simulators in thermohydraulic integral effect test facilities for light water reactors, e. g., an advanced power reactor 1400MWe (APR1400) and a system-integrated modular advanced reactor (SMART). For the design of break simulators of SBLOCA scenarios, the aspect ratio (L/D) is considered to be a key parameter to determine the shape of a break simulator. In this paper, an investigation of critical flow phenomena was performed especially on break simulators for LOCA scenarios in the integral effect test facilities of KAERI, such as ATLAS and FESTA. In this study, various studies on the critical flow models for sub-cooled and/or saturated water were reviewed. For a comparison among the models for the selected test data, discussions of the comparisons on the effect of the diameters, predictions of critical flow models, and break simulators for SBLOCA in the integral effect test facilities were presented

  8. A Study of Critical Flowrate in the Integral Effect Test Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yeongsik; Ryu, Sunguk; Cho, Seok; Yi, Sungjae; Park, Hyunsik [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    In earlier studies, most of the information available in the literature was either for a saturated two-phase flow or a sub-cooled water flow at medium pressure conditions, e. g., up to about 7.0 MPa. The choking is regarded as a condition of maximum possible discharge through a given orifice and/or nozzle exit area. A critical flow rate can be achieved at a choking under the given thermo-hydraulic conditions. The critical flow phenomena were studied extensively in both single-phase and two-phase systems because of its importance in the LOCA analyses of light water reactors and in the design of other engineering areas. Park suggested a modified correlation for predicting the critical flow for sub-cooled water through a nozzle. Recently, Park et al. performed an experimental study on a two-phase critical flow with a noncondensable gas at high pressure conditions. Various experiments of critical flow using sub-cooled water were performed for a modeling of break simulators in thermohydraulic integral effect test facilities for light water reactors, e. g., an advanced power reactor 1400MWe (APR1400) and a system-integrated modular advanced reactor (SMART). For the design of break simulators of SBLOCA scenarios, the aspect ratio (L/D) is considered to be a key parameter to determine the shape of a break simulator. In this paper, an investigation of critical flow phenomena was performed especially on break simulators for LOCA scenarios in the integral effect test facilities of KAERI, such as ATLAS and FESTA. In this study, various studies on the critical flow models for sub-cooled and/or saturated water were reviewed. For a comparison among the models for the selected test data, discussions of the comparisons on the effect of the diameters, predictions of critical flow models, and break simulators for SBLOCA in the integral effect test facilities were presented.

  9. Integrated monitoring and reviewing systems for the Rokkasho Spent Fuel Receipt and Storage Facility

    International Nuclear Information System (INIS)

    Yokota, Yasuhiro; Ishikawa, Masayuki; Matsuda, Yuji

    1998-01-01

    The Rokkasho Spent Fuel Receipt and Storage (RSFS) Facility at the Rokkasho Reprocessing Plant (RRP) in Japan is expected to begin operations in 1998. Effective safeguarding by International Atomic Energy Agency (IAEA) and Japan Atomic Energy Bureau (JAEB) inspectors requires monitoring the time of transfer, direction of movement, and number of spent fuel assemblies transferred. At peak throughput, up to 1,000 spent fuel assemblies will be accepted by the facility in a 90-day period. In order for the safeguards inspector to efficiently review the resulting large amounts of inspection information, an unattended monitoring system was developed that integrates containment and surveillance (C/S) video with radiation monitors. This allows for an integrated review of the facility's radiation data, C/S video, and operator declaration data. This paper presents an outline of the integrated unattended monitoring hardware and associated data reviewing software. The hardware consists of a multicamera optical surveillance (MOS) system radiation monitoring gamma-ray and neutron detector (GRAND) electronics, and an intelligent local operating network (ILON). The ILON was used for time synchronization and MOS video triggers. The new software consists of a suite of tools, each one specific to a single data type: radiation data, surveillance video, and operator declarations. Each tool can be used in a stand-alone mode as a separate ion application or configured to communicate and match time-synchronized data with any of the other tools. A data summary and comparison application (Integrated Review System [IRS]) coordinates the use of all of the data-specific review tools under a single-user interface. It therefore automates and simplifies the importation of data and the data-specific analyses

  10. Report of the Workshop on Petascale Systems Integration for LargeScale Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kramer, William T.C.; Walter, Howard; New, Gary; Engle, Tom; Pennington, Rob; Comes, Brad; Bland, Buddy; Tomlison, Bob; Kasdorf, Jim; Skinner, David; Regimbal, Kevin

    2007-10-01

    There are significant issues regarding Large Scale System integration that are not being addressed in other forums such as current research portfolios or vendor user groups. Unfortunately, the issues in the area of large-scale system integration often fall into a netherworld; not research, not facilities, not procurement, not operations, not user services. Taken together, these issues along with the impact of sub-optimal integration technology means the time required to deploy, integrate and stabilize large scale system may consume up to 20 percent of the useful life of such systems. Improving the state of the art for large scale systems integration has potential to increase the scientific productivity of these systems. Sites have significant expertise, but there are no easy ways to leverage this expertise among them . Many issues inhibit the sharing of information, including available time and effort, as well as issues with sharing proprietary information. Vendors also benefit in the long run from the solutions to issues detected during site testing and integration. There is a great deal of enthusiasm for making large scale system integration a full-fledged partner along with the other major thrusts supported by funding agencies in the definition, design, and use of a petascale systems. Integration technology and issues should have a full 'seat at the table' as petascale and exascale initiatives and programs are planned. The workshop attendees identified a wide range of issues and suggested paths forward. Pursuing these with funding opportunities and innovation offers the opportunity to dramatically improve the state of large scale system integration.

  11. Integrated software package for nuclear material safeguards in a MOX fuel fabrication facility

    International Nuclear Information System (INIS)

    Schreiber, H.J.; Piana, M.; Moussalli, G.; Saukkonen, H.

    2000-01-01

    Since computerized data processing was introduced to Safeguards at large bulk handling facilities, a large number of individual software applications have been developed for nuclear material Safeguards implementation. Facility inventory and flow data are provided in computerized format for performing stratification, sample size calculation and selection of samples for destructive and non-destructive assay. Data is collected from nuclear measurement systems running in attended, unattended mode and more recently from remote monitoring systems controlled. Data sets from various sources have to be evaluated for Safeguards purposes, such as raw data, processed data and conclusions drawn from data evaluation results. They are reported in computerized format at the International Atomic Energy Agency headquarters and feedback from the Agency's mainframe computer system is used to prepare and support Safeguards inspection activities. The integration of all such data originating from various sources cannot be ensured without the existence of a common data format and a database system. This paper describes the fundamental relations between data streams, individual data processing tools, data evaluation results and requirements for an integrated software solution to facilitate nuclear material Safeguards at a bulk handling facility. The paper also explains the basis for designing a software package to manage data streams from various data sources and for incorporating diverse data processing tools that until now have been used independently from each other and under different computer operating systems. (author)

  12. Conjunctive operation of river facilities for integrated water resources management in Korea

    Directory of Open Access Journals (Sweden)

    H. Kim

    2016-10-01

    Full Text Available With the increasing trend of water-related disasters such as floods and droughts resulting from climate change, the integrated management of water resources is gaining importance recently. Korea has worked towards preventing disasters caused by floods and droughts, managing water resources efficiently through the coordinated operation of river facilities such as dams, weirs, and agricultural reservoirs. This has been pursued to enable everyone to enjoy the benefits inherent to the utilization of water resources, by preserving functional rivers, improving their utility and reducing the degradation of water quality caused by floods and droughts. At the same time, coordinated activities are being conducted in multi-purpose dams, hydro-power dams, weirs, agricultural reservoirs and water use facilities (featuring a daily water intake of over 100 000 m3 day−1 with the purpose of monitoring the management of such facilities. This is being done to ensure the protection of public interest without acting as an obstacle to sound water management practices. During Flood Season, each facilities contain flood control capacity by limited operating level which determined by the Regulation Council in advance. Dam flood discharge decisions are approved through the flood forecasting and management of Flood Control Office due to minimize flood damage for both upstream and downstream. The operational plan is implemented through the council's predetermination while dry season for adequate quantity and distribution of water.

  13. Current state of the construction of an integrated test facility for hydrogen risk

    Energy Technology Data Exchange (ETDEWEB)

    Na, Young Su; Hong, Seong-Ho; Hong, Seong-Wan [KAERI, Daejeon (Korea, Republic of)

    2015-05-15

    Experimental research on hydrogen as a combustible gas is important for an assessment of the integrity of a containment building under a severe accident. The Korea Atomic Energy Research Institute (KAERI) is preparing a large-scaled test facility, called SPARC (SPray-Aerosol-Recombiner-Combustion), to estimate the hydrogen behavior such as the distribution, combustion and mitigation. This paper introduces the experimental research activity on hydrogen risk, which was presented at International Congress on Advances in Nuclear Power Plants (ICAPP) this year. The KAERI is preparing a test facility, called SPARC (SPray-Aerosol-Recombiner-Combustion test facility), for an assessment of the hydrogen risk. In the SPARC, hydrogen behavior such as mixing with steam and air, distribution, and combustion in the containment atmosphere will be observed. The SPARC consists of a pressure vessel with a 9.5 m height and 3.4 m in diameter and the operating system to control the thermal hydraulic conditions up to 1.5 MPa at 453 K in a vessel. The temperature, pressure, and gas concentration at various locations will be measured to estimate the atmospheric behavior in a vessel. To install the SPARC, an experimental building, called LIFE (Laboratory for Innovative mitigation of threats from Fission products and Explosion), was constructed at the KAERI site. LIFE has an area of 480 m''2 and height of 18.6 m, and it was designed by considering the experimental safety and specification of a large-sized test facility.

  14. Integrated numerical platforms for environmental dose assessments of large tritium inventory facilities

    International Nuclear Information System (INIS)

    Castro, P.; Ardao, J.; Velarde, M.; Sedano, L.; Xiberta, J.

    2013-01-01

    Related with a prospected new scenario of large inventory tritium facilities [KATRIN at TLK, CANDUs, ITER, EAST, other coming] the prescribed dosimetric limits by ICRP-60 for tritium committed-doses are under discussion requiring, in parallel, to surmount the highly conservative assessments by increasing the refinement of dosimetric-assessments in many aspects. Precise Lagrangian-computations of dosimetric cloud-evolution after standardized (normal/incidental/SBO) tritium cloud emissions are today numerically open to the perfect match of real-time meteorological-data, and patterns data at diverse scales for prompt/early and chronic tritium dose assessments. The trends towards integrated-numerical-platforms for environmental-dose assessments of large tritium inventory facilities under development.

  15. Secondary Waste Cementitious Waste Form Data Package for the Integrated Disposal Facility Performance Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Cantrell, Kirk J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Westsik, Joseph H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Serne, R Jeffrey [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Um, Wooyong [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Cozzi, Alex D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-05-16

    A review of the most up-to-date and relevant data currently available was conducted to develop a set of recommended values for use in the Integrated Disposal Facility (IDF) performance assessment (PA) to model contaminant release from a cementitious waste form for aqueous wastes treated at the Hanford Effluent Treatment Facility (ETF). This data package relies primarily upon recent data collected on Cast Stone formulations fabricated with simulants of low-activity waste (LAW) and liquid secondary wastes expected to be produced at Hanford. These data were supplemented, when necessary, with data developed for saltstone (a similar grout waste form used at the Savannah River Site). Work is currently underway to collect data on cementitious waste forms that are similar to Cast Stone and saltstone but are tailored to the characteristics of ETF-treated liquid secondary wastes. Recommended values for key parameters to conduct PA modeling of contaminant release from ETF-treated liquid waste are provided.

  16. Structural Integrity Program for the Calcined Solids Storage Facilities at the Idaho Nuclear Technology and Engineering Center

    International Nuclear Information System (INIS)

    Bryant, J.W.; Nenni, J.A.

    2003-01-01

    This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, ''Radioactive Waste Management Manual.'' Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities

  17. Structural Integrity Program for the Calcined Solids Storage Facilities at the Idaho Nuclear Technology and Engineering Center

    International Nuclear Information System (INIS)

    Jeffrey Bryant

    2008-01-01

    This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, 'Radioactive Waste Management Manual'. Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities

  18. Integrated disposal Facility Sagebrush Habitat Mitigation Project: FY2007 Compensation Area Monitoring Report

    Energy Technology Data Exchange (ETDEWEB)

    Durham, Robin E.; Sackschewsky, Michael R.

    2007-09-01

    This report summarizes the first year survival of sagebrush seedlings planted as compensatory mitigation for the Integrated Disposal Facility Project. Approximately 42,600 bare root seedlings and 26,000 pluglings were planted at a mitigation site along Army Loop Road in February 2007. Initial baseline monitoring occurred in March 2007, and first summer survival was assessed in September 2007. Overall survival was 19%, with bare root survival being marginally better than pluglings (21% versus 14%). Likely major factors contributing to low survival were late season planting and insufficient soil moisture during seedling establishment.

  19. Software quality assurance plan for the National Ignition Facility integrated computer control system

    International Nuclear Information System (INIS)

    Woodruff, J.

    1996-11-01

    Quality achievement is the responsibility of the line organizations of the National Ignition Facility (NIF) Project. This Software Quality Assurance Plan (SQAP) applies to the activities of the Integrated Computer Control System (ICCS) organization and its subcontractors. The Plan describes the activities implemented by the ICCS section to achieve quality in the NIF Project's controls software and implements the NIF Quality Assurance Program Plan (QAPP, NIF-95-499, L-15958-2) and the Department of Energy's (DOE's) Order 5700.6C. This SQAP governs the quality affecting activities associated with developing and deploying all control system software during the life cycle of the NIF Project

  20. HPCAT: an integrated high-pressure synchrotron facility at the Advanced Photon Source

    International Nuclear Information System (INIS)

    Shen, Guoyin; Chow, Paul; Xiao, Yuming; Sinogeikin, Stanislav; Meng, Yue; Yang, Wenge; Liermann, Hans-Peter; Shebanova, Olga; Rod, Eric; Bommannavar, Arunkumar; Mao, Ho-Kwang

    2008-01-01

    The high pressure collaborative access team (HPCAT) was established to advance cutting edge, multidisciplinary, high-pressure (HP) science and technology using synchrotron radiation at sector 16 of the Advanced Photon Source of Argonne National Laboratory. The integrated HPCAT facility has established four operating beamlines in nine hutches. Two beamlines are split in energy space from the insertion device (16ID) line, whereas the other two are spatially divided into two fans from the bending magnet (16BM) line. An array of novel X-ray diffraction and spectroscopic techniques has been integrated with HP and extreme temperature instrumentation at HPCAT. With a multidisciplinary approach and multi-institution collaborations, the HP program at the HPCAT has been enabling myriad scientific breakthroughs in HP physics, chemistry, materials, and Earth and planetary sciences.

  1. IOTA (Integrable Optics Test Accelerator): facility and experimental beam physics program

    Science.gov (United States)

    Antipov, S.; Broemmelsiek, D.; Bruhwiler, D.; Edstrom, D.; Harms, E.; Lebedev, V.; Leibfritz, J.; Nagaitsev, S.; Park, C. S.; Piekarz, H.; Piot, P.; Prebys, E.; Romanov, A.; Ruan, J.; Sen, T.; Stancari, G.; Thangaraj, C.; Thurman-Keup, R.; Valishev, A.; Shiltsev, V.

    2017-03-01

    The Integrable Optics Test Accelerator (IOTA) is a storage ring for advanced beam physics research currently being built and commissioned at Fermilab. It will operate with protons and electrons using injectors with momenta of 70 and 150 MeV/c, respectively. The research program includes the study of nonlinear focusing integrable optical beam lattices based on special magnets and electron lenses, beam dynamics of space-charge effects and their compensation, optical stochastic cooling, and several other experiments. In this article, we present the design and main parameters of the facility, outline progress to date and provide the timeline of the construction, commissioning and research. The physical principles, design, and hardware implementation plans for the major IOTA experiments are also discussed.

  2. IOTA (Integrable Optics Test Accelerator): Facility and experimental beam physics program

    International Nuclear Information System (INIS)

    Antipov, Sergei; Broemmelsiek, Daniel; Bruhwiler, David; Edstrom, Dean; Harms, Elvin

    2017-01-01

    The Integrable Optics Test Accelerator (IOTA) is a storage ring for advanced beam physics research currently being built and commissioned at Fermilab. It will operate with protons and electrons using injectors with momenta of 70 and 150 MeV/c, respectively. The research program includes the study of nonlinear focusing integrable optical beam lattices based on special magnets and electron lenses, beam dynamics of space-charge effects and their compensation, optical stochastic cooling, and several other experiments. In this article, we present the design and main parameters of the facility, outline progress to date and provide the timeline of the construction, commissioning and research. Finally, the physical principles, design, and hardware implementation plans for the major IOTA experiments are also discussed.

  3. A study on development of Pyro process integrated inactive demonstration facility

    International Nuclear Information System (INIS)

    Cho, I.; Lee, E.; Choung, W.; You, G.; Kim, H.

    2010-10-01

    Since 2007, the Pride (Pyro process integrated inactive demonstration facility) has been developed to demonstrate the integrated engineering-scale pyro processing using natural uranium with surrogate materials. In this paper, safety evaluation on hypothetical accident case is carried out to ensure the release of radioactivity being negligible to the environment and the performance of indoor argon flow for the argon cell has been investigated by means of CFD analysis. The worst accident case, even in the firing of the all uranium metal in argon cell, cause dose rate are negligible comparing to 0.25 Sv of effective dose rate to whole body or 3 Sv of equivalent dose rate to the thyroid preliminary CFD analyses show the temperature and velocity distribution of argon cell, and give the information to change the argon exchange rate and displace the argon supply or exhaust duct. CFD will allow design change and improvements in ventilation systems at lower cost. (Author)

  4. Oxy-Combustion Burner and Integrated Pollutant Removal Research and Development Test Facility

    Energy Technology Data Exchange (ETDEWEB)

    Mark Schoenfield; Manny Menendez; Thomas Ochs; Rigel Woodside; Danylo Oryshchyn

    2012-09-30

    A high flame temperature oxy-combustion test facility consisting of a 5 MWe equivalent test boiler facility and 20 KWe equivalent IPR® was constructed at the Hammond, Indiana manufacturing site. The test facility was operated natural gas and coal fuels and parametric studies were performed to determine the optimal performance conditions and generated the necessary technical data required to demonstrate the technologies are viable for technical and economic scale-up. Flame temperatures between 4930-6120F were achieved with high flame temperature oxy-natural gas combustion depending on whether additional recirculated flue gases are added to balance the heat transfer. For high flame temperature oxy-coal combustion, flame temperatures in excess of 4500F were achieved and demonstrated to be consistent with computational fluid dynamic modeling of the burner system. The project demonstrated feasibility and effectiveness of the Jupiter Oxygen high flame temperature oxy-combustion process with Integrated Pollutant Removal process for CCS and CCUS. With these technologies total parasitic power requirements for both oxygen production and carbon capture currently are in the range of 20% of the gross power output. The Jupiter Oxygen high flame temperature oxy-combustion process has been demonstrated at a Technology Readiness Level of 6 and is ready for commencement of a demonstration project.

  5. CSNI Integral Test Facility Matrices for Validation of Best-Estimate Thermal-Hydraulic Computer Codes

    International Nuclear Information System (INIS)

    Glaeser, H.

    2008-01-01

    Internationally agreed Integral Test Facility (ITF) matrices for validation of realistic thermal hydraulic system computer codes were established. ITF development is mainly for Pressurised Water Reactors (PWRs) and Boiling Water Reactors (BWRs). A separate activity was for Russian Pressurised Water-cooled and Water-moderated Energy Reactors (WWER). Firstly, the main physical phenomena that occur during considered accidents are identified, test types are specified, and test facilities suitable for reproducing these aspects are selected. Secondly, a list of selected experiments carried out in these facilities has been set down. The criteria to achieve the objectives are outlined. In this paper some specific examples from the ITF matrices will also be provided. The matrices will be a guide for code validation, will be a basis for comparisons of code predictions performed with different system codes, and will contribute to the quantification of the uncertainty range of code model predictions. In addition to this objective, the construction of such a matrix is an attempt to record information which has been generated around the world over the last years, so that it is more accessible to present and future workers in that field than would otherwise be the case.

  6. Integrated doses calculation in evacuation scenarios of the neutron generator facility at Missouri S&T

    Energy Technology Data Exchange (ETDEWEB)

    Sharma, Manish K.; Alajo, Ayodeji B., E-mail: alajoa@mst.edu

    2016-08-11

    Any source of ionizing radiations could lead to considerable dose acquisition to individuals in a nuclear facility. Evacuation may be required when elevated levels of radiation is detected within a facility. In this situation, individuals are more likely to take the closest exit. This may not be the most expedient decision as it may lead to higher dose acquisition. The strategy followed in preventing large dose acquisitions should be predicated on the path that offers least dose acquisition. In this work, the neutron generator facility at Missouri University of Science and Technology was analyzed. The Monte Carlo N-Particle (MCNP) radiation transport code was used to model the entire floor of the generator's building. The simulated dose rates in the hallways were used to estimate the integrated doses for different paths leading to exits. It was shown that shortest path did not always lead to minimum dose acquisition and the approach was successful in predicting the expedient path as opposed to the approach of taking the nearest exit.

  7. PWR station blackout transient simulation in the INER integral system test facility

    International Nuclear Information System (INIS)

    Liu, T.J.; Lee, C.H.; Hong, W.T.; Chang, Y.H.

    2004-01-01

    Station blackout transient (or TMLB' scenario) in a pressurized water reactor (PWR) was simulated using the INER Integral System Test Facility (IIST) which is a 1/400 volumetrically-scaled reduce-height and reduce-pressure (RHRP) simulator of a Westinghouse three-loop PWR. Long-term thermal-hydraulic responses including the secondary boil-off and the subsequent primary saturation, pressurization and core uncovery were simulated based on the assumptions of no offsite and onsite power, feedwater and operator actions. The results indicate that two-phase discharge is the major depletion mode since it covers 81.3% of the total amount of the coolant inventory loss. The primary coolant inventory has experienced significant re-distribution during a station blackout transient. The decided parameter to avoid the core overheating is not the total amount of the coolant inventory remained in the primary core cooling system but only the part of coolant left in the pressure vessel. The sequence of significant events during transient for the IIST were also compared with those of the ROSA-IV large-scale test facility (LSTF), which is a 1/48 volumetrically-scaled full-height and full-pressure (FHFP) simulator of a PWR. The comparison indicates that the sequence and timing of these events during TMLB' transient studied in the RHRP IIST facility are generally consistent with those of the FHFP LSTF. (author)

  8. Multilevel examination of facility characteristics, social integration, and health for older adults living in nursing homes.

    Science.gov (United States)

    Leedahl, Skye N; Chapin, Rosemary K; Little, Todd D

    2015-01-01

    Testing a model based on past research and theory, this study assessed relationships between facility characteristics (i.e., culture change efforts, social workers) and residents' social networks and social support across nursing homes; and examined relationships between multiple aspects of social integration (i.e., social networks, social capital, social engagement, social support) and mental and functional health for older adults in nursing homes. Data were collected at nursing homes using a planned missing data design with random sampling techniques. Data collection occurred at the individual-level through in-person structured interviews with older adult nursing home residents (N = 140) and at the facility-level (N = 30) with nursing home staff. The best fitting multilevel structural equation model indicated that the culture change subscale for relationships significantly predicted differences in residents' social networks. Additionally, social networks had a positive indirect relationship with mental and functional health among residents primarily via social engagement. Social capital had a positive direct relationship with both health outcomes. To predict better social integration and mental and functional health outcomes for nursing homes residents, study findings support prioritizing that close relationships exist among staff, residents, and the community as well as increased resident social engagement and social trust. © The Author 2014. Published by Oxford University Press on behalf of The Gerontological Society of America. All rights reserved. For permissions, please e-mail: journals.permissions@oup.com.

  9. Integrating supervision, control and data acquisition—The ITER Neutral Beam Test Facility experience

    Energy Technology Data Exchange (ETDEWEB)

    Luchetta, A., E-mail: adriano.luchetta@igi.cnr.it; Manduchi, G.; Taliercio, C.; Breda, M.; Capobianco, R.; Molon, F.; Moressa, M.; Simionato, P.; Zampiva, E.

    2016-11-15

    Highlights: • The paper describes the experience gained in the integration of different systems for the control and data acquisition system of the ITER Neutral Beam Test Facility. • It describes the way the different frameworks have been integrated. • It reports some lessons learnt during system integration. • It reports some authors’ considerations about the development the ITER CODAC. - Abstract: The ITER Neutral Beam (NBI) Test Facility, under construction in Padova, Italy consists in the ITER full scale ion source for the heating neutral beam injector, referred to as SPIDER, and the full size prototype injector, referred to as MITICA. The Control and Data Acquisition System (CODAS) for SPIDER has been developed and is going to be in operation in 2016. The system is composed of four main components: Supervision, Slow Control, Fast Control and Data Acquisition. These components interact with each other to carry out the system operation and, since they represent a common pattern in fusion experiments, software frameworks have been used for each (set of) component. In order to reuse as far as possible the architecture developed for SPIDER, it is important to clearly define the boundaries and the interfaces among the system components so that the implementation of any component can be replaced without affecting the overall architecture. This work reports the experience gained in the development of SPIDER components, highlighting the importance in the definition of generic interfaces among component, showing how the specific solutions have been adapted to such interfaces and suggesting possible approaches for the development of other ITER subsystems.

  10. Integrating supervision, control and data acquisition—The ITER Neutral Beam Test Facility experience

    International Nuclear Information System (INIS)

    Luchetta, A.; Manduchi, G.; Taliercio, C.; Breda, M.; Capobianco, R.; Molon, F.; Moressa, M.; Simionato, P.; Zampiva, E.

    2016-01-01

    Highlights: • The paper describes the experience gained in the integration of different systems for the control and data acquisition system of the ITER Neutral Beam Test Facility. • It describes the way the different frameworks have been integrated. • It reports some lessons learnt during system integration. • It reports some authors’ considerations about the development the ITER CODAC. - Abstract: The ITER Neutral Beam (NBI) Test Facility, under construction in Padova, Italy consists in the ITER full scale ion source for the heating neutral beam injector, referred to as SPIDER, and the full size prototype injector, referred to as MITICA. The Control and Data Acquisition System (CODAS) for SPIDER has been developed and is going to be in operation in 2016. The system is composed of four main components: Supervision, Slow Control, Fast Control and Data Acquisition. These components interact with each other to carry out the system operation and, since they represent a common pattern in fusion experiments, software frameworks have been used for each (set of) component. In order to reuse as far as possible the architecture developed for SPIDER, it is important to clearly define the boundaries and the interfaces among the system components so that the implementation of any component can be replaced without affecting the overall architecture. This work reports the experience gained in the development of SPIDER components, highlighting the importance in the definition of generic interfaces among component, showing how the specific solutions have been adapted to such interfaces and suggesting possible approaches for the development of other ITER subsystems.

  11. The management of mechanical integrity inspections at small-sized 'Seveso' facilities

    International Nuclear Information System (INIS)

    Bragatto, Paolo A.; Pittiglio, Paolo; Ansaldi, Silvia

    2009-01-01

    The mechanical integrity (MI) of equipment has been controlled at all industrial facilities for many decades. Control methods and intervals are regulated by laws or codes and best practices. In European countries, the legislations implementing the Seveso Directives on the control of major accident hazards require the owner of establishments where hazardous chemicals are handled, to implement a safety management system (SMS). MI controls should be an integral part of the SMS. At large establishments this goal is achieved by adopting the RBI method, but in small-sized establishments with a limited budget and scanty personnel, a heuristic approach is more suitable. This paper demonstrates the feasibility and advantages of integrating SMS and MI by means of a simple method that includes a few basic concepts of RBI without additional costs for operator. This method, supported by a software tool, is resilient as it functions effectively in spite of eventual budget reductions and personnel turnover. The results of MI controls can also be exploited to monitor equipment condition and demonstrate the adequacy of technical systems to the Competent Authorities (CA). Furthermore, the SMS can 'capture' knowledge resulting from MI experience and exploit it for a better understanding of risk

  12. Recharge Data Package for the 2005 Integrated Disposal Facility Performance Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Fayer, Michael J.; Szecsody, Jim E.

    2004-06-30

    Pacific Northwest National Laboratory assisted CH2M Hill Hanford Group, Inc., (CHG) by providing estimates of recharge rates for current conditions and long-term scenarios involving disposal in the Integrated Disposal Facility (IDF). The IDF will be located in the 200 East Area at the Hanford Site and will receive several types of waste including immobilized low-activity waste. The recharge estimates for each scenario were derived from lysimeter and tracer data collected by the IDF PA Project and from modeling studies conducted for the project. Recharge estimates were provided for three specific site features (the surface barrier; possible barrier side slopes; and the surrounding soil) and four specific time periods (pre-Hanford; Hanford operations; surface barrier design life; post-barrier design life). CHG plans to conduct a performance assessment of the latest IDF design and call it the IDF 2005 PA; this recharge data package supports the upcoming IDF 2005 PA.

  13. Software quality assurance plan for the National Ignition Facility integrated computer control system

    Energy Technology Data Exchange (ETDEWEB)

    Woodruff, J.

    1996-11-01

    Quality achievement is the responsibility of the line organizations of the National Ignition Facility (NIF) Project. This Software Quality Assurance Plan (SQAP) applies to the activities of the Integrated Computer Control System (ICCS) organization and its subcontractors. The Plan describes the activities implemented by the ICCS section to achieve quality in the NIF Project`s controls software and implements the NIF Quality Assurance Program Plan (QAPP, NIF-95-499, L-15958-2) and the Department of Energy`s (DOE`s) Order 5700.6C. This SQAP governs the quality affecting activities associated with developing and deploying all control system software during the life cycle of the NIF Project.

  14. Solid secondary waste testing for maintenance of the Hanford Integrated Disposal Facility Performance Assessment - FY 2017

    Energy Technology Data Exchange (ETDEWEB)

    Nichols, Ralph L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Seitz, Roger R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Dixon, Kenneth L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-08-01

    The Waste Treatment and Immobilization Plant (WTP) at Hanford is being constructed to treat 56 million gallons of radioactive waste currently stored in underground tanks at the Hanford site. Operation of the WTP will generate several solid secondary waste (SSW) streams including used process equipment, contaminated tools and instruments, decontamination wastes, high-efficiency particulate air filters (HEPA), carbon adsorption beds, silver mordenite iodine sorbent beds, and spent ion exchange resins (IXr) all of which are to be disposed in the Integrated Disposal Facility (IDF). An applied research and development program was developed using a phased approach to incrementally develop the information necessary to support the IDF PA with each phase of the testing building on results from the previous set of tests and considering new information from the IDF PA calculations. This report contains the results from the exploratory phase, Phase 1 and preliminary results from Phase 2. Phase 3 is expected to begin in the fourth quarter of FY17.

  15. MONITOR: A computer model for estimating the costs of an integral monitored retrievable storage facility

    International Nuclear Information System (INIS)

    Reimus, P.W.; Sevigny, N.L.; Schutz, M.E.; Heller, R.A.

    1986-12-01

    The MONITOR model is a FORTRAN 77 based computer code that provides parametric life-cycle cost estimates for a monitored retrievable storage (MRS) facility. MONITOR is very flexible in that it can estimate the costs of an MRS facility operating under almost any conceivable nuclear waste logistics scenario. The model can also accommodate input data of varying degrees of complexity and detail (ranging from very simple to more complex) which makes it ideal for use in the MRS program, where new designs and new cost data are frequently offered for consideration. MONITOR can be run as an independent program, or it can be interfaced with the Waste System Transportation and Economic Simulation (WASTES) model, a program that simulates the movement of waste through a complete nuclear waste disposal system. The WASTES model drives the MONITOR model by providing it with the annual quantities of waste that are received, stored, and shipped at the MRS facility. Three runs of MONITOR are documented in this report. Two of the runs are for Version 1 of the MONITOR code. A simulation which uses the costs developed by the Ralph M. Parsons Company in the 2A (backup) version of the MRS cost estimate. In one of these runs MONITOR was run as an independent model, and in the other run MONITOR was run using an input file generated by the WASTES model. The two runs correspond to identical cases, and the fact that they gave identical results verified that the code performed the same calculations in both modes of operation. The third run was made for Version 2 of the MONITOR code. A simulation which uses the costs developed by the Ralph M. Parsons Company in the 2B (integral) version of the MRS cost estimate. This run was made with MONITOR being run as an independent model. The results of several cases have been verified by hand calculations

  16. The challenges of integrating multiple safeguards systems in a large nuclear facility

    International Nuclear Information System (INIS)

    Lavietes, A.; Liguori, C.; Pickrell, M.; Plenteda, R.; Sweet, M.

    2009-01-01

    Full-text: Implementing safeguards in a cost-effective manner in large nuclear facilities such as fuel conditioning, fuel reprocessing, and fuel fabrication plants requires the extensive use of instrumentation that is operated in unattended mode. The collected data is then periodically reviewed by the inspectors either on-site at a central location in the facility or remotely in the IAEA offices. A wide variety of instruments are deployed in large facilities, including video surveillance cameras, electronic sealing devices, non-destructive assay systems based on gamma ray and neutron detection, load cells for mass measurement, ID-readers, and other process-specific monitors. The challenge to integrate these different measurement instruments into an efficient, reliable, and secure system requires implementing standardization at various levels throughout the design process. This standardization includes the data generator behaviour and interface, networking solutions, and data security approaches. This standardization will provide a wide range of savings, including reduced training for inspectors and technicians, reduced periodic technical maintenance, reduced spare parts inventory, increased system robustness, and more predictive system behaviour. The development of standard building blocks will reduce the number of data generators required and allow implementation of simplified architectures that do not require local collection computers but rather utilize transmission of the acquired data directly to a central server via Ethernet connectivity. This approach will result in fewer system components and therefore reduced maintenance efforts and improved reliability. This paper discusses in detail the challenges and the subsequent solutions in the various areas that the IAEA Department of Safeguards has committed to pursue as the best sustainable way of maintaining the ability to implement reliable safeguards systems. (author)

  17. Results of 15 years experiments in the PMK-2 integral-type facility for VVERs

    Energy Technology Data Exchange (ETDEWEB)

    Szabados, L.; Ezsoel, G.; Perneczky, L. [KFKI Atomic Energy Research Institute, Budapest (Hungary)

    2001-07-01

    Due to the specific features of the VVER-440/213-type reactors the transient behaviour of such a reactor system is different from the usual PWR system behaviour. To provide an experimental database for the transient behaviour of VVER systems the PMK integral-type facility, the scaled down model of the Paks NPP was designed and constructed in the early 1980's. Since the start-up of the facility 48 experiments have been performed. It was confirmed through the experiments that the facility is a suitable tool for the computer code validation experiments and to the identification of basic thermal-hydraulic phenomena occurring during plant accidents. High international interest was shown by the four Standard Problem Exercises of the IAEA and by the projects financed by the EU-PHARE. A wide range of small- and medium-size LOCA sequences have been studied to know the performance and effectiveness of ECC systems and to evaluate the thermal-hydraulic safety of the core. Extensive studies have been performed to investigate the one- and two-phase natural circulation, the effect of disturbances coming from the secondary circuit and to validate the effectiveness of accident management measures like bleed and feed. The VVER-specific case, the opening of the SG collector cover was also extensively investigated. Examples given in the report show a few results of experiments and the results of calculation analyses performed for validation purposes of codes like RELAP5, ATHLET and CATHARE. There are some other white spots in Cross Reference Matrices for VVER reactors and, therefore, further experiments are planned to perform tests primarily in further support of accident management measures at low power states of plants to facilitate the improved safety management of VVER-440-type reactors. (authors)

  18. Results of 15 years experiments in the PMK-2 integral-type facility for VVERs

    International Nuclear Information System (INIS)

    Szabados, L.; Ezsoel, G.; Perneczky, L.

    2001-01-01

    Due to the specific features of the VVER-440/213-type reactors the transient behaviour of such a reactor system is different from the usual PWR system behaviour. To provide an experimental database for the transient behaviour of VVER systems the PMK integral-type facility, the scaled down model of the Paks NPP was designed and constructed in the early 1980's. Since the start-up of the facility 48 experiments have been performed. It was confirmed through the experiments that the facility is a suitable tool for the computer code validation experiments and to the identification of basic thermal-hydraulic phenomena occurring during plant accidents. High international interest was shown by the four Standard Problem Exercises of the IAEA and by the projects financed by the EU-PHARE. A wide range of small- and medium-size LOCA sequences have been studied to know the performance and effectiveness of ECC systems and to evaluate the thermal-hydraulic safety of the core. Extensive studies have been performed to investigate the one- and two-phase natural circulation, the effect of disturbances coming from the secondary circuit and to validate the effectiveness of accident management measures like bleed and feed. The VVER-specific case, the opening of the SG collector cover was also extensively investigated. Examples given in the report show a few results of experiments and the results of calculation analyses performed for validation purposes of codes like RELAP5, ATHLET and CATHARE. There are some other white spots in Cross Reference Matrices for VVER reactors and, therefore, further experiments are planned to perform tests primarily in further support of accident management measures at low power states of plants to facilitate the improved safety management of VVER-440-type reactors. (authors)

  19. Design and first integral test of MUSE facility in ALPHA program

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hyun-sun; Yamano, Norihiro; Maruyama, Yu; Moriyama, Kiyofumi; Kudo, Tamotsu; Yang, Yanhua; Sugimoto, Jun [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-03-01

    Vapor explosion (Steam explosion or energetic Fuel-Coolant Interaction) is a phenomenon in which a hot liquid rapidly releases its internal energy into a surrounding colder and more volatile liquid when these liquids come into a sudden contact. This rapid energy release leads to rapid vapor production within a timescale short compared to vapor expansion causes local pressurization similar to an explosion and eventually threatens the surroundings by dynamic pressures and the subsequent expansion. It has been recognized that the energetics of vapor explosions strongly depend on the initial mixing geometry established by the contact of hot and cold liquids. Therefore, a new program has been initiated to investigate the energetics of vapor explosions in various contact geometries; i.e., pouring, stratified, coolant and melt injection modes in a facility which is able to measure the energy conversion ratio and eventually to provide data to evaluate the mechanistic analytical models. In the report, this new facility, called MUSE (MUlti-configuration in Steam Explosions), and the results of the first integral test are described in detail. (author)

  20. Transition from depressurization to long term cooling in AP600 scaled integral test facilities

    International Nuclear Information System (INIS)

    Bessette, D.E.; Marzo, M. di

    1999-01-01

    A novel light water reactor design called the AP600 has been proposed by the Westinghouse Electric Corporation. In the evaluation of this plant's behavior during a small break loss of coolant accident (LOCA), the crucial transition to low pressure, long-term cooling is marked by the injection of the gravitationally driven flow from the in-containment refueling water storage tank (IRWST). The onset of this injection is characterized by intermittency in the IRWST flow. This happens at a time when the reactor vessel reaches its minimum inventory. Therefore, it is important to understand and scale the behavior of the integral experimental test facilities during this portion of the transient. The explanation is that the periodic liquid drains and refills of the pressurizer are the reason for the intermittent behavior. The momentum balance for the surge line yields the nondimensional parameter controlling this process. Data from one of the three experimental facilities represent the phenomena well at the prototypical scale. The impact of the intermittent IRWST injection on the safe plant operation is assessed and its implications are successfully resolved. The oscillation is found to result from, in effect, excess water in the primary system and it is not of safety significance. (orig.)

  1. Development of a Remote Handling System in an Integrated Pyroprocessing Facility

    Directory of Open Access Journals (Sweden)

    Hyo Jik Lee

    2013-10-01

    Full Text Available Over the course of a decade-long research programme, the Korea Atomic Energy Research Institute (KAERI has developed several remote handling systems for use in pyroprocessing research facilities. These systems are now used successfully for the operation and maintenance of processing equipment. The most recent remote handling system is the bridge-transported dual arm servo-manipulator system (BDSM, which is used for remote operation at the world's largest pyroprocess integrated inactive demonstration facility (PRIDE. Accurate and reliable servo-control is the basic requirement for the BDSM to accomplish any given tasks successfully in a hotcell environment. To achieve this end, the hardware and software of a digital signal processor-based remote control system were fully custom-developed and implemented to control the BDSM. To reduce the residual vibration of the BDSM, several input profiles, including input shaping, were carefully chosen and evaluated. Furthermore, a time delay controller was employed to achieve good tracking performance and systematic gain tuning. The experimental results demonstrate that the applied control algorithms are more effective than conventional approaches. The BDSM successfully completed its performance tests at a mock-up and was installed at PRIDE for real-world operation. The remote handling system at KAERI is expected to advance the actualization of pyroprocessing.

  2. Chemical Entity Semantic Specification: Knowledge representation for efficient semantic cheminformatics and facile data integration

    Science.gov (United States)

    2011-01-01

    Background Over the past several centuries, chemistry has permeated virtually every facet of human lifestyle, enriching fields as diverse as medicine, agriculture, manufacturing, warfare, and electronics, among numerous others. Unfortunately, application-specific, incompatible chemical information formats and representation strategies have emerged as a result of such diverse adoption of chemistry. Although a number of efforts have been dedicated to unifying the computational representation of chemical information, disparities between the various chemical databases still persist and stand in the way of cross-domain, interdisciplinary investigations. Through a common syntax and formal semantics, Semantic Web technology offers the ability to accurately represent, integrate, reason about and query across diverse chemical information. Results Here we specify and implement the Chemical Entity Semantic Specification (CHESS) for the representation of polyatomic chemical entities, their substructures, bonds, atoms, and reactions using Semantic Web technologies. CHESS provides means to capture aspects of their corresponding chemical descriptors, connectivity, functional composition, and geometric structure while specifying mechanisms for data provenance. We demonstrate that using our readily extensible specification, it is possible to efficiently integrate multiple disparate chemical data sources, while retaining appropriate correspondence of chemical descriptors, with very little additional effort. We demonstrate the impact of some of our representational decisions on the performance of chemically-aware knowledgebase searching and rudimentary reaction candidate selection. Finally, we provide access to the tools necessary to carry out chemical entity encoding in CHESS, along with a sample knowledgebase. Conclusions By harnessing the power of Semantic Web technologies with CHESS, it is possible to provide a means of facile cross-domain chemical knowledge integration with full

  3. Conceptual design of an ALICE Tier-2 centre. Integrated into a multi-purpose computing facility

    Energy Technology Data Exchange (ETDEWEB)

    Zynovyev, Mykhaylo

    2012-06-29

    This thesis discusses the issues and challenges associated with the design and operation of a data analysis facility for a high-energy physics experiment at a multi-purpose computing centre. At the spotlight is a Tier-2 centre of the distributed computing model of the ALICE experiment at the Large Hadron Collider at CERN in Geneva, Switzerland. The design steps, examined in the thesis, include analysis and optimization of the I/O access patterns of the user workload, integration of the storage resources, and development of the techniques for effective system administration and operation of the facility in a shared computing environment. A number of I/O access performance issues on multiple levels of the I/O subsystem, introduced by utilization of hard disks for data storage, have been addressed by the means of exhaustive benchmarking and thorough analysis of the I/O of the user applications in the ALICE software framework. Defining the set of requirements to the storage system, describing the potential performance bottlenecks and single points of failure and examining possible ways to avoid them allows one to develop guidelines for selecting the way how to integrate the storage resources. The solution, how to preserve a specific software stack for the experiment in a shared environment, is presented along with its effects on the user workload performance. The proposal for a flexible model to deploy and operate the ALICE Tier-2 infrastructure and applications in a virtual environment through adoption of the cloud computing technology and the 'Infrastructure as Code' concept completes the thesis. Scientific software applications can be efficiently computed in a virtual environment, and there is an urgent need to adapt the infrastructure for effective usage of cloud resources.

  4. Conceptual design of an ALICE Tier-2 centre. Integrated into a multi-purpose computing facility

    International Nuclear Information System (INIS)

    Zynovyev, Mykhaylo

    2012-01-01

    This thesis discusses the issues and challenges associated with the design and operation of a data analysis facility for a high-energy physics experiment at a multi-purpose computing centre. At the spotlight is a Tier-2 centre of the distributed computing model of the ALICE experiment at the Large Hadron Collider at CERN in Geneva, Switzerland. The design steps, examined in the thesis, include analysis and optimization of the I/O access patterns of the user workload, integration of the storage resources, and development of the techniques for effective system administration and operation of the facility in a shared computing environment. A number of I/O access performance issues on multiple levels of the I/O subsystem, introduced by utilization of hard disks for data storage, have been addressed by the means of exhaustive benchmarking and thorough analysis of the I/O of the user applications in the ALICE software framework. Defining the set of requirements to the storage system, describing the potential performance bottlenecks and single points of failure and examining possible ways to avoid them allows one to develop guidelines for selecting the way how to integrate the storage resources. The solution, how to preserve a specific software stack for the experiment in a shared environment, is presented along with its effects on the user workload performance. The proposal for a flexible model to deploy and operate the ALICE Tier-2 infrastructure and applications in a virtual environment through adoption of the cloud computing technology and the 'Infrastructure as Code' concept completes the thesis. Scientific software applications can be efficiently computed in a virtual environment, and there is an urgent need to adapt the infrastructure for effective usage of cloud resources.

  5. Using a qualitative approach for understanding hospital-affiliated integrated clinical and fitness facilities: characteristics and members' experiences.

    Science.gov (United States)

    Yang, Jingzhen; Kingsbury, Diana; Nichols, Matthew; Grimm, Kristin; Ding, Kele; Hallam, Jeffrey

    2015-06-19

    With health care shifting away from the traditional sick care model, many hospitals are integrating fitness facilities and programs into their clinical services in order to support health promotion and disease prevention at the community level. Through a series of focus groups, the present study assessed characteristics of hospital-affiliated integrated facilities located in Northeast Ohio, United States and members' experiences with respect to these facilities. Adult members were invited to participate in a focus group using a recruitment flyer. A total of 6 focus groups were conducted in 2013, each lasting one hour, ranging from 5 to 12 participants per group. The responses and discussions were recorded and transcribed verbatim, then analyzed independently by research team members. Major themes were identified after consensus was reached. The participants' average age was 57, with 56.8% currently under a doctor's care. Four major themes associated with integrated facilities and members' experiences emerged across the six focus groups: 1) facility/program, 2) social atmosphere, 3) provider, and 4) member. Within each theme, several sub-themes were also identified. A key feature of integrated facilities is the availability of clinical and fitness services "under one roof". Many participants remarked that they initially attended physical therapy, becoming members of the fitness facility afterwards, or vice versa. The participants had favorable views of and experiences with the superior physical environment and atmosphere, personal attention, tailored programs, and knowledgeable, friendly, and attentive staff. In particular, participants favored the emphasis on preventive care and the promotion of holistic health and wellness. These results support the integration of wellness promotion and programming with traditional medical care and call for the further evaluation of such a model with regard to participants' health outcomes.

  6. Final deactivation project report on the Integrated Process Demonstration Facility, Building 7602 Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1997-09-01

    The purpose of this report is to document the condition of the Integrated Process Demonstration Facility (Building 7602) at Oak Ridge National Laboratory (ORNL) after completion of deactivation activities by the High Ranking Facilities Deactivation Project (HRFDP). This report identifies the activities conducted to place the facility in a safe and environmentally sound condition prior to transfer to the U.S. Department of Energy (DOE) Environmental Restoration EM-40 Program. This report provides a history and description of the facility prior to commencing deactivation activities and documents the condition of the building after completion of all deactivation activities. Turnover items, such as the Post-Deactivation Surveillance and Maintenance (S ampersand M) Plan, remaining hazardous and radioactive materials inventory, radiological controls, Safeguards and Security, and supporting documentation provided in the Office of Nuclear Material and Facility Stabilization Program (EM-60) Turnover package are discussed

  7. Integrated assessment of thermal hydraulic processes in W7-X fusion experimental facility

    Energy Technology Data Exchange (ETDEWEB)

    Kaliatka, T., E-mail: tadas.kaliatka@lei.lt; Uspuras, E.; Kaliatka, A.

    2017-02-15

    Highlights: • The model of Ingress of Coolant Event experiment facility was developed using the RELAP5 code. • Calculation results were compared with Ingress of Coolant Event experiment data. • Using gained experience, the numerical model of Wendelstein 7-X facility was developed. • Performed analysis approved pressure increase protection system for LOCA event. - Abstract: Energy received from the nuclear fusion reaction is one of the most promising options for generating large amounts of carbon-free energy in the future. However, physical and technical problems existing in this technology are complicated. Several experimental nuclear fusion devices around the world have already been constructed, and several are under construction. However, the processes in the cooling system of the in-vessel components, vacuum vessel and pressure increase protection system of nuclear fusion devices are not widely studied. The largest amount of radioactive materials is concentrated in the vacuum vessel of the fusion device. Vacuum vessel is designed for the vacuum conditions inside the vessel. Rupture of the in-vessel components of the cooling system pipe may lead to a sharp pressure increase and possible damage of the vacuum vessel. To prevent the overpressure, the pressure increase protection system should be designed and implemented. Therefore, systematic and detailed experimental and numerical studies, regarding the thermal-hydraulic processes in cooling system, vacuum vessel and pressure increase protection system, are important and relevant. In this article, the numerical investigation of thermal-hydraulic processes in cooling systems of in-vessel components, vacuum vessels and pressure increase protection system of fusion devices is presented. Using the experience gained from the modelling of “Ingress of Coolant Event” experimental facilities, the numerical model of Wendelstein 7-X (W7-X) experimental fusion device was developed. The integrated analysis of the

  8. Integration of the PHIN RF Gun into the CLIC Test Facility

    CERN Document Server

    Döbert, Steffen

    2006-01-01

    CERN is a collaborator within the European PHIN project, a joint research activity for Photo injectors within the CARE program. A deliverable of this project is an rf Gun equipped with high quantum efficiency Cs2Te cathodes and a laser to produce the nominal beam for the CLIC Test Facility (CTF3). The nominal beam for CTF3 has an average current of 3.5 A, 1.5 GHz bunch repetition frequency and a pulse length of 1.5 ìs (2332 bunches) with quite tight stability requirements. In addition a phase shift of 180 deg is needed after each train of 140 ns for the special CLIC combination scheme. This rf Gun will be tested at CERN in fall 2006 and shall be integrated as a new injector into the CTF3 linac, replacing the existing injector consisting of a thermionic gun and a subharmonic bunching system. The paper studies the optimal integration into the machine trying to optimize transverse and longitudinal phase space of the beam while respecting the numerous constraints of the existing accelerator. The presented scheme...

  9. Integration of knowledge management system for the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Iguchi, Yukihiro; Yanagihara, Satoshi

    2016-01-01

    The decommissioning of a nuclear facility is a long term project, handling information which begins from the design, construction and operation. Moreover, the decommissioning project is likely to be extended because of the lack of the waste disposal site especially in Japan. In this situation, because the transfer of knowledge and education to the next generation is a crucial issue, integration and implementation of a system for knowledge management is necessary in order to solve it. For this purpose, the total system of decommissioning knowledge management system (KMS) is proposed. In this system, we have to arrange, organize and systematize the data and information of the plant design, maintenance history, trouble events, waste management records etc. The collected data, information and records should be organized by computer support system e.g. data base system. It becomes a base of the explicit knowledge. Moreover, measures of extracting tacit knowledge from retiring employees are necessary. The experience of the retirees should be documented as much as possible through effective questionnaire or interview process. The integrated knowledge mentioned above should be used for the planning, implementation of dismantlement or education for the future generation. (author)

  10. Integrated, long term, sustainable, cost effective biosolids management at a large Canadian wastewater treatment facility.

    Science.gov (United States)

    Leblanc, R J; Allain, C J; Laughton, P J; Henry, J G

    2004-01-01

    The Greater Moncton Sewerage Commission's 115,000 m3/d advanced, chemically assisted primary wastewater treatment facility located in New Brunswick, Canada, has developed an integrated, long term, sustainable, cost effective programme for the management and beneficial utilization of biosolids from lime stabilized raw sludge. The paper overviews biosolids production, lime stabilization, conveyance, and odour control followed by an indepth discussion of the wastewater sludge as a resource programme, namely: composting, mine site reclamation, landfill cover, land application for agricultural use, tree farming, sod farm base as a soil enrichment, topsoil manufacturing. The paper also addresses the issues of metals, pathogens, organic compounds, the quality control program along with the regulatory requirements. Biosolids capital and operating costs are presented. Research results on removal of metals from primary sludge using a unique biological process known as BIOSOL as developed by the University of Toronto, Canada to remove metals and destroy pathogens are presented. The paper also discusses an ongoing cooperative research project with the Université de Moncton where various mixtures of plant biosolids are composted with low quality soil. Integration, approach to sustainability and "cumulative effects" as part of the overall biosolids management strategy are also discussed.

  11. Integrated, long term, sustainable, cost effective biosolids management at a large Canadian wastewater treatment facility

    Energy Technology Data Exchange (ETDEWEB)

    LeBlance, R.J.; Allain, C.J.; Laughton, P.J.; Henry, J.G.

    2003-07-01

    The Greater Moncton Sewerage Commission's 115 000 m{sup 3}/d advanced, chemically assisted primary wastewater treatment facility located in New Brunswick, Canada, has developed an integrated, long term, sustainable, cost effective programme for the management and beneficial utilization of biosolids from lime stabilized raw sludge. The paper overviews biosolids production, lime stabilization, conveyance, and odour control followed by an indepth discussion of the wastewater sludge as a resource programme, namely: composting, mine site reclamation, landfill cover, land application for agricultural use, tree farming, sod farm base as a soil enrichment, topsoil manufacturing. The paper also addresses the issues of metals, pathogens, organic compounds, the quality control program along with the regulatory requirements. Biosolids capital and operating costs are presented. Research results on removal of metals from primary sludge using a unique biological process known as BIOSOL as developed by the University of Toronto, Canada to remove metals and destroy pathogens are presented. The paper also discusses an ongoing cooperative research project with the Universite de Moncton where various mixtures of plant biosolids are composted with low quality soil. Integration, approach to sustainability and ''cumulative effects'' as part of the overall biosolids management strategy is also discussed. (author)

  12. NOMINATION FOR THE PROJECT MANAGEMENT INSTITUTE (PMI) PROJECT OF THE YEAR AWARD. INTEGRATED DISPOSAL FACILITY (IDF)

    International Nuclear Information System (INIS)

    MCLELLAN, G.W.

    2007-01-01

    CH2M HILL Hanford Group, Inc. (CH2M HILL) is pleased to nominate the Integrated Disposal Facility (IDF) project for the Project Management Institute's consideration as 2007 Project of the Year, Built for the U.S, Department of Energy's (DOE) Office of River Protection (ORP) at the Hanford Site, the IDF is the site's first Resource Conservation and Recovery Act (RCRA)-compliant disposal facility. The IDF is important to DOE's waste management strategy for the site. Effective management of the IDF project contributed to the project's success. The project was carefully managed to meet three Tri-Party Agreement (TPA) milestones. The completed facility fully satisfied the needs and expectations of the client, regulators and stakeholders. Ultimately, the project, initially estimated to require 48 months and $33.9 million to build, was completed four months ahead of schedule and $11.1 million under budget. DOE directed construction of the IDF to provide additional capacity for disposing of low-level radioactive and mixed (i.e., radioactive and hazardous) solid waste. The facility needed to comply with federal and Washington State environmental laws and meet TPA milestones. The facility had to accommodate over one million cubic yards of the waste material, including immobilized low-activity waste packages from the Waste Treatment Plant (WTP), low-level and mixed low-level waste from WTP failed melters, and alternative immobilized low-activity waste forms, such as bulk-vitrified waste. CH2M HILL designed and constructed a disposal facility with a redundant system of containment barriers and a sophisticated leak-detection system. Built on a 168-area, the facility's construction met all regulatory requirements. The facility's containment system actually exceeds the state's environmental requirements for a hazardous waste landfill. Effective management of the IDF construction project required working through highly political and legal issues as well as challenges with

  13. NOMINATION FOR THE PROJECT MANAGEMENT INSTITUTE (PMI) PROJECT OF THE YEAR AWARD INTEGRATED DISPOSAL FACILITY (IDF)

    Energy Technology Data Exchange (ETDEWEB)

    MCLELLAN, G.W.

    2007-02-07

    CH2M HILL Hanford Group, Inc. (CH2M HILL) is pleased to nominate the Integrated Disposal Facility (IDF) project for the Project Management Institute's consideration as 2007 Project of the Year, Built for the U.S, Department of Energy's (DOE) Office of River Protection (ORP) at the Hanford Site, the IDF is the site's first Resource Conservation and Recovery Act (RCRA)-compliant disposal facility. The IDF is important to DOE's waste management strategy for the site. Effective management of the IDF project contributed to the project's success. The project was carefully managed to meet three Tri-Party Agreement (TPA) milestones. The completed facility fully satisfied the needs and expectations of the client, regulators and stakeholders. Ultimately, the project, initially estimated to require 48 months and $33.9 million to build, was completed four months ahead of schedule and $11.1 million under budget. DOE directed construction of the IDF to provide additional capacity for disposing of low-level radioactive and mixed (i.e., radioactive and hazardous) solid waste. The facility needed to comply with federal and Washington State environmental laws and meet TPA milestones. The facility had to accommodate over one million cubic yards of the waste material, including immobilized low-activity waste packages from the Waste Treatment Plant (WTP), low-level and mixed low-level waste from WTP failed melters, and alternative immobilized low-activity waste forms, such as bulk-vitrified waste. CH2M HILL designed and constructed a disposal facility with a redundant system of containment barriers and a sophisticated leak-detection system. Built on a 168-area, the facility's construction met all regulatory requirements. The facility's containment system actually exceeds the state's environmental requirements for a hazardous waste landfill. Effective management of the IDF construction project required working through highly political and legal

  14. Geochemical Data Package for the 2005 Hanford Integrated Disposal Facility Performance Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Krupka, Kenneth M.; Serne, R JEFFREY.; Kaplan, D I.

    2004-09-30

    CH2M HILL Hanford Group, Inc. (CH2M HILL) is designing and assessing the performance of an integrated disposal facility (IDF) to receive low-level waste (LLW), mixed low-level waste (MLLW), immobilized low-activity waste (ILAW), and failed or decommissioned melters. The CH2M HILL project to assess the performance of this disposal facility is the Hanford IDF Performance Assessment (PA) activity. The goal of the Hanford IDF PA activity is to provide a reasonable expectation that the disposal of the waste is protective of the general public, groundwater resources, air resources, surface-water resources, and inadvertent intruders. Achieving this goal will require prediction of contaminant migration from the facilities. This migration is expected to occur primarily via the movement of water through the facilities, and the consequent transport of dissolved contaminants in the vadose zone to groundwater where contaminants may be re-introduced to receptors via drinking water wells or mixing in the Columbia River. Pacific Northwest National Laboratory (PNNL) assists CH2M HILL in their performance assessment activities. One of the PNNL tasks is to provide estimates of the geochemical properties of the materials comprising the IDF, the disturbed region around the facility, and the physically undisturbed sediments below the facility (including the vadose zone sediments and the aquifer sediments in the upper unconfined aquifer). The geochemical properties are expressed as parameters that quantify the adsorption of contaminants and the solubility constraints that might apply for those contaminants that may exceed solubility constraints. The common parameters used to quantify adsorption and solubility are the distribution coefficient (Kd) and the thermodynamic solubility product (Ksp), respectively. In this data package, we approximate the solubility of contaminants using a more simplified construct, called the solution concentration limit, a constant value. The Kd values and

  15. Technical and economic feasibility study for the reactivation of the integral test facility of IPEN/CNEN Nuclear Engineering Center

    Energy Technology Data Exchange (ETDEWEB)

    Biaty, Flávia P.; Rocha, Marcelo da S.; Oliveira, Otávio L. de, E-mail: flavia.biaty@usp.br, E-mail: msrocha@ipen.br, E-mail: otavioluis@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

    2017-07-01

    The Integral Test Facility of Nuclear Engineering Center (CEN/IPEN/CNEN-SP), known as 'Loop 70', is a semi-industrial thermal-hydraulic test facility and can operate as a BWR (Boiling Water Reactor) or a PWR (Pressurizing Water Reactor) mode. Designed and built in the 1980's, it is currently disabled. The experimental circuits ('test loop') are facilities that reproduce the thermohydraulic and fluid dynamic conditions that occur inside a reactor and are used to simulate the practical reality which it is not possible to be obtained through mathematical models. In this context, this research project aims the development of a Business Plan to analyze the technical and economic feasibility related to the reactivation of the facility. This methodology (adapted to the government sector) is a decision-making tool that will offer a wide perspective of the project, set the guidelines and actions that will define the future of the facility and provide a general rule to make investments on it. This paper presents the historic aspects to better understand the Loop 70's current situation. It also presents information about similar facilities around the world, services that can be offered (thermal-hydraulics parameters measurements, equipment qualification and transient analysis due accident situations), results of the strategic analysis (SWOT) performed, specific goals for each critical success or failure factor of the facility, financial aspects related to the reactivation and an overview of the facility's perspectives. (author)

  16. Technical and economic feasibility study for the reactivation of the integral test facility of IPEN/CNEN Nuclear Engineering Center

    International Nuclear Information System (INIS)

    Biaty, Flávia P.; Rocha, Marcelo da S.; Oliveira, Otávio L. de

    2017-01-01

    The Integral Test Facility of Nuclear Engineering Center (CEN/IPEN/CNEN-SP), known as 'Loop 70', is a semi-industrial thermal-hydraulic test facility and can operate as a BWR (Boiling Water Reactor) or a PWR (Pressurizing Water Reactor) mode. Designed and built in the 1980's, it is currently disabled. The experimental circuits ('test loop') are facilities that reproduce the thermohydraulic and fluid dynamic conditions that occur inside a reactor and are used to simulate the practical reality which it is not possible to be obtained through mathematical models. In this context, this research project aims the development of a Business Plan to analyze the technical and economic feasibility related to the reactivation of the facility. This methodology (adapted to the government sector) is a decision-making tool that will offer a wide perspective of the project, set the guidelines and actions that will define the future of the facility and provide a general rule to make investments on it. This paper presents the historic aspects to better understand the Loop 70's current situation. It also presents information about similar facilities around the world, services that can be offered (thermal-hydraulics parameters measurements, equipment qualification and transient analysis due accident situations), results of the strategic analysis (SWOT) performed, specific goals for each critical success or failure factor of the facility, financial aspects related to the reactivation and an overview of the facility's perspectives. (author)

  17. The application of integrated safety management principles to the Tritium Extraction Facility project

    International Nuclear Information System (INIS)

    Hickman, M.O.; Viviano, R.R.

    2000-01-01

    The DOE has developed a program that is accomplishing a heightened safety posture across the complex. The Integrated Safety Management (ISM) System (ISMS) program utilizes five core functions and seven guiding principles as the basis for implementation. The core functions define the work scope, analyze the hazards, develop and implement hazard controls, perform the work, and provide feedback for improvement. The guiding principles include line management responsibility, clear roles and responsibilities, competence per responsibilities, identification of safety standards/requirements, tailored hazard control, balanced priorities, and operations authorization. There exists an unspecified eighth principle, that is, worker involvement. A program requiring the direct involvement of the employees who are actually performing the work has been shown to be quite an effective method of communicating safety requirements, controlling work in a safe manner, and reducing safety violations and injuries. The Tritium Extraction Facility (TEF) projects, a component of the DOE's Commercial Light Water Reactor Tritium Production program, has taken the ISM principles and core functions and applied them to the project's design. The task of the design team is to design a facility and systems that will meet the production requirements of the DOE tritium mission as well as a design that minimizes the workers' exposure to adverse safety situations and hazards/hazardous materials. During the development of the preliminary design for the TEF, design teams consisted of not only designers but also personnel who had operational experience in the existing tritium and personnel who had operational experience in the existing tritium and personnel who had specialized experience from across the DOE complex. This design team reviewed multiple documents associated with the TEF operation in order to identify and document the hazards associated with the tritium process. These documents include hazards

  18. Development of integrated containment and surveillance system for fast critical facility FCA. Portal and penetration monitors

    International Nuclear Information System (INIS)

    Mukaiyama, Takehiko; Ogawa, Hironobu; Yokota, Yasuhiro.

    1998-01-01

    Manpower and radiation exposure problems, accompanied by frequent Non Destructive Assay (NDA) based inspections at the Fast Critical Facility FCA of Japan Atomic Energy Research Institute (JAERI), are a burden for both the inspectorates and the facility operator. In the hope of alleviating these burdens, the development of containment and surveillance measures for the FCA was initiated in 1979. The integrated containment and surveillance system consists of a portal monitor and a penetration monitor. The reactor building provides an ideal containment measure because of its explosion-proof, airtight structure and limited number of penetrations. The function of the portal monitor is to detect undeclared removal of nuclear material from the reactor building through the doorway. The penetration monitor is designed for surveillance of diversion routes through containment boundaries, and of safeguards related activities for bypassing the portal monitor. The combination of monitoring by the penetration monitor of containment boundaries and all their penetrations except for the doorway, and monitoring by the portal monitor, provides complete coverage of realistic diversion routes. The development of the system was completed in 1988 and the field trial test was conducted for the period of twelve running months. The final report on the field trial was concluded on January 1990. The major conclusion of the report was that the system is effective, reliable and efficient. Following this successful conclusion, the International Atomic Energy Agency (IAEA) accepted the system for meeting its safeguards goals at the FCA on condition that an independent IAEA authentication equipment is provided. The development of the authentication equipment is accomplished as an separate Japan Support Programme for Agency Safeguards (JASPAS) task. (author)

  19. Remediation Approach for the Integrated Facility Disposition Project at the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Kirk, P.G.; Stephens, Jr.J.M.

    2009-01-01

    The Integrated Facility Disposition Project (IFDP) is a multi-billion-dollar remediation effort being conducted by the U.S. Department of Energy (DOE) Office of Environmental Management in Oak Ridge, Tennessee. The scope of the IFDP encompasses remedial actions related to activities conducted over the past 65 years at the Oak Ridge National Laboratory (ORNL) and the Y-12 National Security Complex (Y-12). Environmental media and facilities became contaminated as a result of operations, leaks, spills, and past waste disposal practices. ORNL's mission includes energy, environmental, nuclear security, computational, and materials research and development. Remediation activities will be implemented at ORNL as part of IFDP scope to meet remedial action objectives established in existing and future decision documents. Remedial actions are necessary (1) to comply with environmental regulations to reduce human health and environmental risk and (2) to release strategic real estate needed for modernization initiatives at ORNL. The scope of remedial actions includes characterization, waste management, transportation and disposal, stream restoration, and final remediation of contaminated soils, sediments, and groundwater. Activities include removal of at or below-grade substructures such as slabs, underground utilities, underground piping, tanks, basins, pits, ducts, equipment housings, manholes, and concrete-poured structures associated with equipment housings and basement walls/floors/columns. Many interim remedial actions involving groundwater and surface water that have not been completed are included in the IFDP remedial action scope. The challenges presented by the remediation of Bethel Valley at ORNL are formidable. The proposed approach to remediation endeavors to use the best available technologies and technical approaches from EPA and other federal agencies and lessons learned from previous cleanup efforts. The objective is to minimize cost, maximize remedial

  20. Monitoring System for Storm Readiness and Recovery of Test Facilities: Integrated System Health Management (ISHM) Approach

    Science.gov (United States)

    Figueroa, Fernando; Morris, Jon; Turowski, Mark; Franzl, Richard; Walker, Mark; Kapadia, Ravi; Venkatesh, Meera; Schmalzel, John

    2010-01-01

    Severe weather events are likely occurrences on the Mississippi Gulf Coast. It is important to rapidly diagnose and mitigate the effects of storms on Stennis Space Center's rocket engine test complex to avoid delays to critical test article programs, reduce costs, and maintain safety. An Integrated Systems Health Management (ISHM) approach and technologies are employed to integrate environmental (weather) monitoring, structural modeling, and the suite of available facility instrumentation to provide information for readiness before storms, rapid initial damage assessment to guide mitigation planning, and then support on-going assurance as repairs are effected and finally support recertification. The system is denominated Katrina Storm Monitoring System (KStorMS). Integrated Systems Health Management (ISHM) describes a comprehensive set of capabilities that provide insight into the behavior the health of a system. Knowing the status of a system allows decision makers to effectively plan and execute their mission. For example, early insight into component degradation and impending failures provides more time to develop work around strategies and more effectively plan for maintenance. Failures of system elements generally occur over time. Information extracted from sensor data, combined with system-wide knowledge bases and methods for information extraction and fusion, inference, and decision making, can be used to detect incipient failures. If failures do occur, it is critical to detect and isolate them, and suggest an appropriate course of action. ISHM enables determining the condition (health) of every element in a complex system-of-systems or SoS (detect anomalies, diagnose causes, predict future anomalies), and provide data, information, and knowledge (DIaK) to control systems for safe and effective operation. ISHM capability is achieved by using a wide range of technologies that enable anomaly detection, diagnostics, prognostics, and advise for control: (1

  1. Status of the National Ignition Facility Integrated Computer Control System (ICCS) on the Path to Ignition

    International Nuclear Information System (INIS)

    Lagin, L J; Bettenhauasen, R C; Bowers, G A; Carey, R W; Edwards, O D; Estes, C M; Demaret, R D; Ferguson, S W; Fisher, J M; Ho, J C; Ludwigsen, A P; Mathisen, D G; Marshall, C D; Matone, J M; McGuigan, D L; Sanchez, R J; Shelton, R T; Stout, E A; Tekle, E; Townsend, S L; Van Arsdall, P J; Wilson, E F

    2007-01-01

    The National Ignition Facility (NIF) at the Lawrence Livermore National Laboratory is a stadium-sized facility under construction that will contain a 192-beam, 1.8-Megajoule, 500-Terawatt, ultraviolet laser system together with a 10-meter diameter target chamber with room for multiple experimental diagnostics. NIF is the world's largest and most energetic laser experimental system, providing a scientific center to study inertial confinement fusion (ICF) and matter at extreme energy densities and pressures. NIF's laser beams are designed to compress fusion targets to conditions required for thermonuclear burn, liberating more energy than required to initiate the fusion reactions. NIF is comprised of 24 independent bundles of 8 beams each using laser hardware that is modularized into more than 6,000 line replaceable units such as optical assemblies, laser amplifiers, and multifunction sensor packages containing 60,000 control and diagnostic points. NIF is operated by the large-scale Integrated Computer Control System (ICCS) in an architecture partitioned by bundle and distributed among over 800 front-end processors and 50 supervisory servers. NIF's automated control subsystems are built from a common object-oriented software framework based on CORBA distribution that deploys the software across the computer network and achieves interoperation between different languages and target architectures. A shot automation framework has been deployed during the past year to orchestrate and automate shots performed at the NIF using the ICCS. In December 2006, a full cluster of 48 beams of NIF was fired simultaneously, demonstrating that the independent bundle control system will scale to full scale of 192 beams. At present, 72 beams have been commissioned and have demonstrated 1.4-Megajoule capability of infrared light. During the next two years, the control system will be expanded to include automation of target area systems including final optics, target positioners and

  2. Status of the National Ignition Facility Integrated Computer Control System (ICCS) on the path to ignition

    International Nuclear Information System (INIS)

    Lagin, L.J.; Bettenhausen, R.C.; Bowers, G.A.; Carey, R.W.; Edwards, O.D.; Estes, C.M.; Demaret, R.D.; Ferguson, S.W.; Fisher, J.M.; Ho, J.C.; Ludwigsen, A.P.; Mathisen, D.G.; Marshall, C.D.; Matone, J.T.; McGuigan, D.L.; Sanchez, R.J.; Stout, E.A.; Tekle, E.A.; Townsend, S.L.; Van Arsdall, P.J.

    2008-01-01

    The National Ignition Facility (NIF) at the Lawrence Livermore National Laboratory is a stadium-sized facility under construction that will contain a 192-beam, 1.8-MJ, 500-TW, ultraviolet laser system together with a 10-m diameter target chamber with room for multiple experimental diagnostics. NIF is the world's largest and most energetic laser experimental system, providing a scientific center to study inertial confinement fusion (ICF) and matter at extreme energy densities and pressures. NIF's laser beams are designed to compress fusion targets to conditions required for thermonuclear burn, liberating more energy than required to initiate the fusion reactions. NIF is comprised of 24 independent bundles of eight beams each using laser hardware that is modularized into more than 6000 line replaceable units such as optical assemblies, laser amplifiers, and multi-function sensor packages containing 60,000 control and diagnostic points. NIF is operated by the large-scale Integrated Computer Control System (ICCS) in an architecture partitioned by bundle and distributed among over 800 front-end processors and 50 supervisory servers. NIF's automated control subsystems are built from a common object-oriented software framework based on CORBA distribution that deploys the software across the computer network and achieves interoperation between different languages and target architectures. A shot automation framework has been deployed during the past year to orchestrate and automate shots performed at the NIF using the ICCS. In December 2006, a full cluster of 48 beams of NIF was fired simultaneously, demonstrating that the independent bundle control system will scale to full scale of 192 beams. At present, 72 beams have been commissioned and have demonstrated 1.4-MJ capability of infrared light. During the next 2 years, the control system will be expanded in preparation for project completion in 2009 to include automation of target area systems including final optics

  3. Development of a model forecasting Dermanyssus gallinae's population dynamics for advancing Integrated Pest Management in laying hen facilities

    NARCIS (Netherlands)

    Mul, Monique F.; Riel, van Johannes; Roy, Lise; Zoons, Johan; Andre, Geert; George, David R.; Meerburg, Bastiaan G.; Dicke, Marcel; Mourik, van Simon; Groot Koerkamp, Peter W.G.

    2017-01-01

    The poultry red mite, Dermanyssus gallinae, is the most significant pest of egg laying hens in many parts of the world. Control of D. gallinae could be greatly improved with advanced Integrated Pest Management (IPM) for D. gallinae in laying hen facilities. The development of a model forecasting

  4. X-ray facility for the ground calibration of the X-ray monitor JEM-X on board INTEGRAL

    DEFF Research Database (Denmark)

    Loffredo, G.; Pelliciari, C.; Frontera, F.

    2003-01-01

    We describe the X-ray facility developed for the calibration of the X-ray monitor JEM-X on board the INTEGRAL satellite. The apparatus allowed the scanning of the detector geometric area with a pencil beam of desired energy over the major part of the passband of the instrument. The monochromatic...

  5. Integrative approach for wastewater treatment facilities with biomass transformation into energy

    Directory of Open Access Journals (Sweden)

    Anker Yaakov

    2017-01-01

    Full Text Available Current industrial environmental regulations favor processes with Integrative Pollution Prevention and Control (IPPC. While several systems are regarded by different international directives as IPPC Best Available Techniques or Technologies (BAT, none of these systems are capable handling various pollutants of both gaseous and aquatic effluents. Additional hinder to a BAT-IPPC complete procedure are hazardous or uneconomical byproducts of the IPPC processes and significant auxiliary costs for consumables and energy. The current research and subsequent projects are aimed to the development of a Biological Integrative Pollution Prevention and Control (Bio-IPPC system. Such system can be incorporated in various industrial processes, in a way that the byproduct is without hazardous potential and may be used as an economical raw material. The main initiative and heart of these systems is a micro-algae reactor, which is capable of treating various types of industrial pollutants both in the gaseous and aquatic phases. The algae nutrition is through thin-film circulation of the aquatic effluent and the reactor atmosphere is enriched by flue gases. The excessive algal biomass may be utilized for economic purposes starting with animal feedstock, through organic fertilizer and as industrial raw material for biofuels production or direct energy production. The first industrial project is a wastewater (WW polishing stage to an industry zone WW treatment facility, which ensures high level effluent purification and assimilation of greenhouse gases, which are released during the WW bioremediation process. The second industrial application aims to treat aquatic and gaseous effluents from coal propelled power plants. The raw algal material from both projects although very different, is used for the development of new efficient scheme for bioethanol production. In summary, the system presented is an actual Bio-IPPC that can interactively treat several industrial

  6. Sextant: an expert system for transient analysis of nuclear reactors and integral test facilities

    International Nuclear Information System (INIS)

    Barbet, N.; Dumas, M.; Mihelich, G.

    1987-01-01

    Expert systems provide a new way of dealing with the computer-aided management of nuclear plants by combining several knowledge bases and reasoning modes together with a set of numerical models for real-time analysis of transients. New development tools are required together with metaknowledge bases handling temporal hypothetical reasoning and planning. They have to be efficient and robust because during a transient, neither measurements nor models, nor scenarios are hold as absolute references. SEXTANT is a general purpose physical analyzer intended to provide a pattern and avoid duplication of general tools and knowledge bases for similar applications. It combines several knowledge bases concerning measurements, models and qualitative behavior of PWR with a mechanism of conjecture-refutation and a set of simplified models matching the current physical state. A prototype is under assessment by dealing with integral test facility transients. For its development, SEXTANT requires a powerful shell. SPIRAL is such a toolkit, oriented towards online analysis of complex processes and already used in several applications

  7. Design and cost estimate for the SRL integrated hot off gas facility using selective adsorption

    International Nuclear Information System (INIS)

    Pence, D.T.; Kirstein, B.E.

    1981-07-01

    Based on the results of an engineering-scale demonstration program, a design and cost estimate were performed for a 25-m 3 /h (15-ft 3 /min) capacity pilot plant demonstration system using selective adsorption technology for installation at the Integrated Hot Off Gas Facility at the Savannah River Plant. The design includes provisions for the destruction of NO/sub x/ and the concentration and removal of radioisotopes of ruthenium, iodine-129, tritiated water vapor, carbon-14 contaminated carbon dioxide, and krypton-85. The nobel gases are separated by the use of selective adsorption on mordenite-type zeolites. The theory of noble gas adsorption on zeolites is essentially the same as that for the adsorption of noble gases on activated charcoals. Considerable detail is provided regarding the application of the theory to adsorbent bed designs and operation. The design is based on a comprehensive material balance and appropriate heat transfer calculations. Details are provided on techniques and procedures used for heating, cooling, and desorbing the adsorbent columns. Analyses are also given regarding component and arrangement selection and includes discussions on alternative arrangements. The estimated equipment costs for the described treatment system is about $1,400,000. The cost estimate includes a detailed equipment list of all the major component items in the design. Related technical issues and estimated system performance are also discussed

  8. Design and cost estimate for the SRL integrated hot off gas facility using selective adsorption

    Energy Technology Data Exchange (ETDEWEB)

    Pence, D T; Kirstein, B E

    1981-07-01

    Based on the results of an engineering-scale demonstration program, a design and cost estimate were performed for a 25-m/sup 3//h (15-ft/sup 3//min) capacity pilot plant demonstration system using selective adsorption technology for installation at the Integrated Hot Off Gas Facility at the Savannah River Plant. The design includes provisions for the destruction of NO/sub x/ and the concentration and removal of radioisotopes of ruthenium, iodine-129, tritiated water vapor, carbon-14 contaminated carbon dioxide, and krypton-85. The nobel gases are separated by the use of selective adsorption on mordenite-type zeolites. The theory of noble gas adsorption on zeolites is essentially the same as that for the adsorption of noble gases on activated charcoals. Considerable detail is provided regarding the application of the theory to adsorbent bed designs and operation. The design is based on a comprehensive material balance and appropriate heat transfer calculations. Details are provided on techniques and procedures used for heating, cooling, and desorbing the adsorbent columns. Analyses are also given regarding component and arrangement selection and includes discussions on alternative arrangements. The estimated equipment costs for the described treatment system is about $1,400,000. The cost estimate includes a detailed equipment list of all the major component items in the design. Related technical issues and estimated system performance are also discussed.

  9. Integrated representation of hydropower facilities in an operational flood warning system for a mountainous watershed

    Directory of Open Access Journals (Sweden)

    Claude Aurélien

    2016-01-01

    Full Text Available An integrated flood forecasting system adapted to mountain basins is under construction at the flood forecasting service of the French Northern Alps (SPCAN, whose jurisdiction area covers the whole Isère River basin (12000km2. Most parts of this area are harnessed for hydropower production, thus modifying flows at all the main sections of the stream network. A semi-distributed conceptual modeling approach was chosen for predicting warning levels at daily time step. Before giving results on the strategic warning point of Montmèlian, simulations on two representative sub-basins of about 1000 km2 are detailed. The first sub-basin includes the large Sautet dam, on the Drac River. The second, on the Isère River, includes the large dam of Tignes and is characterized by multiple diversions. The influence of hydroelectric facilities was analyzed for reconstituting natural flows. Then, a two-steps modeling strategy was deployed: firstly, natural reconstituted flows were simulated; next, the effect of hydroelectric works was introduced, considering the operating status of the main reservoirs and of the water intakes, the latter being aggregated together as a unique equivalent device. While keeping a reasonable level of model complexity, the developed tool provides accurate simulations of observed flood events and is planned to be further used in real-time.

  10. Safety, reliability, risk management and human factors: an integrated engineering approach applied to nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Vasconcelos, Vanderley de; Silva, Eliane Magalhaes Pereira da; Costa, Antonio Carlos Lopes da; Reis, Sergio Carneiro dos [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)], e-mail: vasconv@cdtn.br, e-mail: silvaem@cdtn.br, e-mail: aclc@cdtn.br, e-mail: reissc@cdtn.br

    2009-07-01

    Nuclear energy has an important engineering legacy to share with the conventional industry. Much of the development of the tools related to safety, reliability, risk management, and human factors are associated with nuclear plant processes, mainly because the public concern about nuclear power generation. Despite the close association between these subjects, there are some important different approaches. The reliability engineering approach uses several techniques to minimize the component failures that cause the failure of the complex systems. These techniques include, for instance, redundancy, diversity, standby sparing, safety factors, and reliability centered maintenance. On the other hand system safety is primarily concerned with hazard management, that is, the identification, evaluation and control of hazards. Rather than just look at failure rates or engineering strengths, system safety would examine the interactions among system components. The events that cause accidents may be complex combinations of component failures, faulty maintenance, design errors, human actions, or actuation of instrumentation and control. Then, system safety deals with a broader spectrum of risk management, including: ergonomics, legal requirements, quality control, public acceptance, political considerations, and many other non-technical influences. Taking care of these subjects individually can compromise the completeness of the analysis and the measures associated with both risk reduction, and safety and reliability increasing. Analyzing together the engineering systems and controls of a nuclear facility, their management systems and operational procedures, and the human factors engineering, many benefits can be realized. This paper proposes an integration of these issues based on the application of systems theory. (author)

  11. Hazards and accident analyses, an integrated approach, for the Plutonium Facility at Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Pan, P.Y.; Goen, L.K.; Letellier, B.C.; Sasser, M.K.

    1995-01-01

    This paper describes an integrated approach to perform hazards and accident analyses for the Plutonium Facility at Los Alamos National Laboratory. A comprehensive hazards analysis methodology was developed that extends the scope of the preliminary/process hazard analysis methods described in the AIChE Guidelines for Hazard Evaluations. Results fro the semi-quantitative approach constitute a full spectrum of hazards. For each accident scenario identified, there is a binning assigned for the event likelihood and consequence severity. In addition, each accident scenario is analyzed for four possible sectors (workers, on-site personnel, public, and environment). A screening process was developed to link the hazard analysis to the accident analysis. Specifically the 840 accident scenarios were screened down to about 15 accident scenarios for a more through deterministic analysis to define the operational safety envelope. The mechanics of the screening process in the selection of final scenarios for each representative accident category, i.e., fire, explosion, criticality, and spill, is described

  12. Safety, reliability, risk management and human factors: an integrated engineering approach applied to nuclear facilities

    International Nuclear Information System (INIS)

    Vasconcelos, Vanderley de; Silva, Eliane Magalhaes Pereira da; Costa, Antonio Carlos Lopes da; Reis, Sergio Carneiro dos

    2009-01-01

    Nuclear energy has an important engineering legacy to share with the conventional industry. Much of the development of the tools related to safety, reliability, risk management, and human factors are associated with nuclear plant processes, mainly because the public concern about nuclear power generation. Despite the close association between these subjects, there are some important different approaches. The reliability engineering approach uses several techniques to minimize the component failures that cause the failure of the complex systems. These techniques include, for instance, redundancy, diversity, standby sparing, safety factors, and reliability centered maintenance. On the other hand system safety is primarily concerned with hazard management, that is, the identification, evaluation and control of hazards. Rather than just look at failure rates or engineering strengths, system safety would examine the interactions among system components. The events that cause accidents may be complex combinations of component failures, faulty maintenance, design errors, human actions, or actuation of instrumentation and control. Then, system safety deals with a broader spectrum of risk management, including: ergonomics, legal requirements, quality control, public acceptance, political considerations, and many other non-technical influences. Taking care of these subjects individually can compromise the completeness of the analysis and the measures associated with both risk reduction, and safety and reliability increasing. Analyzing together the engineering systems and controls of a nuclear facility, their management systems and operational procedures, and the human factors engineering, many benefits can be realized. This paper proposes an integration of these issues based on the application of systems theory. (author)

  13. Investigation on integrity of JMTR concrete structures, cooling system and utility facilities

    International Nuclear Information System (INIS)

    Ebisawa, Hiroyuki; Tobita, Kenji; Fukasaku, Akitomi; Kaminaga, Masanori

    2010-02-01

    The condition of facilities and components to be used for re-operation of the Japan Materials Testing Reactor (JMTR) from FY2011, was investigated before the refurbishment work. An investigation of aged components (aged-investigation) was carried out for concrete structures of the JMTR reactor building, exhaust stack, trench, canal, filter banks and for aged components of tanks in the primary cooling system, heat exchangers, pipes in the secondary cooling system, cooling tower, emergency generators and so on, in order to identify their integrity. The aged-investigation was carried out from the beginning of FY2007. As a result, cracks of concrete structures such as the exhaust stack, a foundation of the UCL (Utility Cooling Line) elevated water tank were repaired and pipe linings of secondary cooling system were replaced. Motors of primary cooling pumps, pumps in the secondary cooling system and in other systems were decided to replace from viewpoints of future maintenance and improvement of reliability. Other components and the reactor building were decided to use continuously for a long-term by appropriate maintenance activities based on the long-term maintenance plan. In this paper, the aged-investigation for the JMTR reactor building, heat exchangers and emergency generators is presented. (author)

  14. Integrated leak rate testing of the fast flux test facility reactor containment building

    International Nuclear Information System (INIS)

    James, E.B.; Farabee, O.A.; Bliss, R.J.

    1978-01-01

    The initial Integrated Leak Rate Test (ILRT) of the Fast Flux Test Facility containment building was performed from May 27 to June 2, 1978. The test was conducted in air with systems vented and with the containment recirculating coolers in operation. 10 psig and 5 psig tests were run using the absolute pressure test method. The measured leakage rates were .033% Vol/24 hr. and -.0015% Vol/24 hrs. respectively. Subsequent verification tests at both 10 psig and 5 psig proved that the test equipment was operating properly and it was sensitive enough to detect leaks at low pressures. This ILRT was performed at a lower pressure than any previous ILRT on a reactor containment structure in the United States. While the initial design requirements for ice condenser containments called for a part pressure test at 6 psig, the tests were waived due to the apparent statistical problems of data analysis and the repeatability of the data itself at such low pressure. In contrast to this belief, both the 5 and 10 psig ILRT's were performed in a successful manner at FFTF

  15. 15 years of The Hungarian integral type test facility: horizontal SG related PMK-2 experiments

    International Nuclear Information System (INIS)

    Perneczky, L.; Ezsoel, G.; Guba, A.; Szabados, L.

    2001-01-01

    support of accident management (AM) procedures. During the 15 operational years - from May 1986 onwards with the first of four IAEA Standard Problem Exercise tests - 48 different experiments, including cold and hot leg break LOCA, primary-to-secondary leakage (PRISE), loss of flow, loss of feedwater, disturbances of natural circulation, etc. tests were performed on this integral type test facility. An overview on 11 experiments related to the operational behaviour of horizontal steam generators performed in framework of national research projects IAEA Technical Co-operation Project RER/9/004 (Standard Problem Exercises) and three EU PHARE projects (in co-operation with AEAT, FRAMATOM, SIEMENS, IPSN, GRS, FZR and VVER owner countries) is given in the first part of paper. In the second part results of two types of tests in shutdown condition with RELAP5 post-test analysis may be of interest to the computer simulation of the horizontal SG too - are summarised. (orig.)

  16. Investigation of primary-to-secondary leakage accident on the PSB-VVER integral test facility

    International Nuclear Information System (INIS)

    Lipatov, I.A.; Dremin, G.I.; Galtchanskaya, S.A.; Chmal, I.I.; Moloshnikov, A.S.; Gorbunov, Y.S.; Antonova, A.I.; Elkin, I.V.

    2001-01-01

    The full text follows. The paper presents the main results from the test on primary-to-secondary leakage of 100 mm in equivalent diameter. The test was performed on the PSB-VVER integral test facility. PSB-VVER is a 4-loops scaled down model of primary system of NPP with VVER-1000 Russian type reactor. Volume - power scale is about 1/300 while elevation scale is 1/1. All components of the primary system of the reference NPP are modeled on PSB-VVER. Both passive (accumulators) and active (high and low pressure) ECCSs, pressurizer spray and relief circuits, feed water system and atmospheric dumping system (ADS) as well as the primary circuit gas remove emergency system are also simulated. The primary-to-secondary leakage was simulated using an external break line which connects the upper part of the hot header to SG water volume. The break line included a break nozzle (a cylindrical channel d = 5.8 mm, l/d = 10 with sharp inlet edge), quick-acting valve and two-phase mass flow rate measurement system. In addition loss of off-site power at the moment when a scram-signal is generated was assumed in the experiment. Thus the accident is to be considered as a beyond-design-basic one. The loss of off-site power results in the following: -main circulation pump shutdown; -pressurizer heaters switching off; -HPIS water cooling flow rate and number of points of water injection are reduced The study focuses on the adequacy of the associated accident management (AM) procedure developed by EDO ''GIDROPRESS'' as a General Designer of VVER-type reactors. The AM-procedure was adopted to the PSB-VVER test facility conditions using CATHARE (France) and DINAMIKA (Russia) codes analysis. The AM-procedure in PSB-VVER is as follows: after about 30 min of the onset of the accident, when the accident type and the localization of the SG affected become evident for the operator, he closes all the main steam isolation valves, inhibits the ADS actuation in the affected SG and begins to remove

  17. Investigation of primary-to-secondary leakage accident on the PSB-VVER integral test facility

    Energy Technology Data Exchange (ETDEWEB)

    Lipatov, I.A.; Dremin, G.I.; Galtchanskaya, S.A.; Chmal, I.I.; Moloshnikov, A.S.; Gorbunov, Y.S.; Antonova, A.I. [Electrogorsk Research and Engineering Center, EREC, Moscow (Russian Federation); Elkin, I.V. [RRC ' ' Kurchatov Institute, Moscow (Russian Federation)

    2001-07-01

    The full text follows. The paper presents the main results from the test on primary-to-secondary leakage of 100 mm in equivalent diameter. The test was performed on the PSB-VVER integral test facility. PSB-VVER is a 4-loops scaled down model of primary system of NPP with VVER-1000 Russian type reactor. Volume - power scale is about 1/300 while elevation scale is 1/1. All components of the primary system of the reference NPP are modeled on PSB-VVER. Both passive (accumulators) and active (high and low pressure) ECCSs, pressurizer spray and relief circuits, feed water system and atmospheric dumping system (ADS) as well as the primary circuit gas remove emergency system are also simulated. The primary-to-secondary leakage was simulated using an external break line which connects the upper part of the hot header to SG water volume. The break line included a break nozzle (a cylindrical channel d = 5.8 mm, l/d = 10 with sharp inlet edge), quick-acting valve and two-phase mass flow rate measurement system. In addition loss of off-site power at the moment when a scram-signal is generated was assumed in the experiment. Thus the accident is to be considered as a beyond-design-basic one. The loss of off-site power results in the following: -main circulation pump shutdown; -pressurizer heaters switching off; -HPIS water cooling flow rate and number of points of water injection are reduced The study focuses on the adequacy of the associated accident management (AM) procedure developed by EDO ''GIDROPRESS'' as a General Designer of VVER-type reactors. The AM-procedure was adopted to the PSB-VVER test facility conditions using CATHARE (France) and DINAMIKA (Russia) codes analysis. The AM-procedure in PSB-VVER is as follows: after about 30 min of the onset of the accident, when the accident type and the localization of the SG affected become evident for the operator, he closes all the main steam isolation valves, inhibits the ADS actuation in the affected SG

  18. Application of Framework for Integrating Safety, Security and Safeguards (3Ss) into the Design Of Used Nuclear Fuel Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    Badwan, Faris M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Demuth, Scott F [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-01-06

    Department of Energy’s Office of Nuclear Energy, Fuel Cycle Research and Development develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development focused on used nuclear fuel recycling and waste management to meet U.S. needs. Used nuclear fuel is currently stored onsite in either wet pools or in dry storage systems, with disposal envisioned in interim storage facility and, ultimately, in a deep-mined geologic repository. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Integrating safety, security, and safeguards (3Ss) fully in the early stages of the design process for a new nuclear facility has the potential to effectively minimize safety, proliferation, and security risks. The 3Ss integration framework could become the new national and international norm and the standard process for designing future nuclear facilities. The purpose of this report is to develop a framework for integrating the safety, security and safeguards concept into the design of Used Nuclear Fuel Storage Facility (UNFSF). The primary focus is on integration of safeguards and security into the UNFSF based on the existing Nuclear Regulatory Commission (NRC) approach to addressing the safety/security interface (10 CFR 73.58 and Regulatory Guide 5.73) for nuclear power plants. The methodology used for adaptation of the NRC safety/security interface will be used as the basis for development of the safeguards /security interface and later will be used as the basis for development of safety and safeguards interface. Then this will complete the integration cycle of safety, security, and safeguards. The overall methodology for integration of 3Ss will be proposed, but only the integration of safeguards and security will be applied to the design of the

  19. Integrating industry nuclear codes and standards into United States Department of Energy facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jacox, J.

    1995-02-01

    Recently the United States Department of Energy (DOE) has mandated facilities under their jurisdiction use various industry Codes and Standards developed for civilian power reactors that operate under U.S. Nuclear Regulatory Commission License. While this is a major step forward in putting all our nuclear facilities under common technical standards there are always problems associated with implementing such advances. This paper will discuss some of the advantages and problems experienced to date. These include the universal challenge of educating new users of any technical documents, repeating errors made by the NRC licensed facilities over the years and some unique problems specific to DOE facilities.

  20. Bioregenerative Life Support Experiment for 90-days in a Closed Integrative Experimental Facility LUNAR PALACE 1

    Science.gov (United States)

    Liu, Hong

    A 90-day bioregenerative life support experiment with three-member crew was carried out in the closed integrative experimental facility, LUNAR PALACE 1 regenerating basic living necessities and disposing wastes to provide life support for crew. It was composed of higher plant module, animal module, and waste treatment module. The higher plant module included wheat, chufa, pea, carrot and green leafy vegetables, with aim to satisfy requirement of 60% plant food and 100% O2 and water for crew. The yellow mealworm was selected as animal module to provide partial animal protein for crew, and reared on plant inedible biomass. The higher plant and yellow mealworm were both cultivated and harvested in the conveyor-type manner. The partial plant inedible biomass and human feces were mixed and co- fermented in the waste treatment module for preparation of soil-like substrate by bioconversion, maintaining gas balance and increasing closure degree. Meanwhile, in the waste treatment module, the water and partial nitrogen from human urine were recovered by physical-chemical means. Circulation of O2 and water as well as food supply from crops cultivated in the LUNAR PALACE 1 were investigated and calculated, and simultaneously gas exchange, mass flow among different components and system closure degree were also analyzed, respectively. Furthermore, the system robustness with respect to internal variation was tested and evaluated by sensitivity analysis of the aggregative index consisting of key performance indicators like crop yield, gaseous equilibrium concentration, microbial community composition, biogenic elements dynamics, etc., and comprehensively evaluating the operating state, to number change of crew from 2 to 4 during the 90-day closed experiment period.

  1. CSNI Integral test facility validation matrix for the assessment of thermal-hydraulic codes for LWR LOCA and transients

    International Nuclear Information System (INIS)

    1996-07-01

    This report deals with an internationally agreed integral test facility (ITF) matrix for the validation of best estimate thermal-hydraulic computer codes. Firstly, the main physical phenomena that occur during the considered accidents are identified, test types are specified, and test facilities suitable for reproducing these aspects are selected. Secondly, a life of selected experiments carried out in these facilities has been set down. The criteria to achieve the objectives are outlined. The construction of such a matrix is an attempt to collect together in a systematic way the best sets of openly available test data for code validation, assessment and improvement, including quantitative assessment of uncertainties in the modelling of phenomena by the codes. In addition to this objective, it is an attempt to record information which has been generated around the world over the last 20 years so that it is more accessible to present and future workers in that field than would otherwise be the case

  2. Multi-site risk-based project planning, optimization, sequencing, & budgeting process and tool for the integrated facility disposition project

    International Nuclear Information System (INIS)

    Nelson, J.G.; Castillo, C.; Huntsman, J.; Killoy, S.; Lucek, H.; Marks, T.C.

    2011-01-01

    Faced with the Department of Energy (DOE) Complex Transformation, National Nuclear Security Administration (NNSA) was tasked with developing an integrated plan for the decommissioning of over 400 facilities and 300 environmental remediation units, as well as the many reconfiguration and modernization projects at the Oak Ridge National Laboratory (ORNL) and Y-12 Complex. Manual scheduling of remediation activities is time-consuming and inherently introduces bias of the scheduler or organization into the process. Clearly a well-defined process, quantitative risk-based tool was needed to develop an objective, unbiased baseline sequence and schedule with a sound technical foundation for the Integrated Facility Disposition Project (IFDP). Faced with limited available data, innovation was needed to extrapolate intelligent relative data for key risk parameters based on known data elements. The IFDP Supermodel was customized and expanded to provide this capability for conceptual planning of diverse project portfolios and multiple sites. (author)

  3. Proceeding of 26th domestic symposium on present and future of integrity monitoring technology in nuclear power generation facilities

    International Nuclear Information System (INIS)

    2000-06-01

    As the 26th domestic symposium of Atomic Energy Research Committee, the Japan Welding Engineering Society, the symposium was held titled as 'Current status and future of integrity monitoring techniques in nuclear power facilities'. Six speakers gave lectures titled as 'Maintenance and integrity monitoring in nuclear power plants', 'Present status of fatigue and creep-fatigue monitoring techniques in the US', 'Fatigue monitoring system in Tsuruga-1 nuclear power station', 'Vibration monitoring technique of rotational machine', 'SCC monitoring with electrochemical noise analysis' and Monitoring technique for corrosive environments and crack shape'. (T. Tanaka)

  4. Proceeding of 31st domestic symposium on failure events and integrity evaluation of nuclear power generation facilities

    International Nuclear Information System (INIS)

    2003-07-01

    As the 31st domestic symposium of Atomic Energy Research Committee, the Japan Welding Engineering Society, the symposium was held titled as 'Damage events and integrity evaluations of nuclear power facilities'. Six speakers gave lectures titled as 'Damages of structural materials in the LWR plants and their measures', 'Inspection and integrity evaluation method of SCC in the BWR plants', 'Measures with chloride SCC of piping', 'High cycle fatigue damage events of small diameter pipes and their measures', 'Management of SCC in in-core instrumentation thimbles' and 'Japanese lost ten years and American and other leaps'. (T. Tanaka)

  5. Integration of bicycling and walking facilities into the infrastructure of urban communities.

    Science.gov (United States)

    2012-02-01

    Several manuals, handbooks and web resources exist to provide varied guidance on planning for and designing bicycle and pedestrian facilities, yet there are no specific indications about which of the varied treatments in these guides work well for us...

  6. Development of an Integrated Leachate Treatment Solution for the Port Granby Waste Management Facility - 12429

    Energy Technology Data Exchange (ETDEWEB)

    Conroy, Kevin W. [Golder Associates Inc., Lakewood, Colorado (United States); Vandergaast, Gerald [Atomic Energy of Canada Limited, Port Hope, Ontario (Canada)

    2012-07-01

    The Port Granby Project (the Project) is located near the north shore of Lake Ontario in the Municipality of Clarington, Ontario, Canada. The Project consists of relocating approximately 450,000 m{sup 3} of historic Low-Level Radioactive Waste (LLRW) and contaminated soil from the existing Port Granby Waste Management Facility (WMF) to a proposed Long-Term Waste Management Facility (LTWMF) located adjacent to the WMF. The LTWMF will include an engineered waste containment facility, a Wastewater Treatment Plant (WTP), and other ancillary facilities. A series of bench- and pilot-scale test programs have been conducted to identify preferred treatment processes to be incorporated into the WTP to treat wastewater generated during the construction, closure and post-closure periods at the WMF/LTWMF. (authors)

  7. Straighttalk. The ideal master facility plan begins with business strategy and integrates operational improvement.

    Science.gov (United States)

    Powder, Scott; Brown, Richard E; Haupert, John M; Smith, Ryder

    2007-04-02

    Given the scarcity of capital to meet ever-growing demands for healthcare services, master facility planning has become more important than ever. Executives must align their master facility plans with their overall business strategy, incorporating the best in care- and service-delivery models. In this installment of Straight Talk, executives from two health systems--Advocate Health Care in Oak Brook, Ill. and Parkland Health & Hospital System in Dallas--discuss master facility planning. Modern Healthcare and PricewaterhouseCoopers present Straight Talk. The session on master facility planning was held on March 8, 2007 at Modern Healthcare's Chicago Headquarters. Charles Lauer, former vice president of publishing and editorial director at Modern Healthcare, was the moderator.

  8. National Ignition Facility sub-system design requirements integrated timing system SSDR 1.5.3

    International Nuclear Information System (INIS)

    Wiedwald, J.; Van Aersau, P.; Bliss, E.

    1996-01-01

    This System Design Requirement document establishes the performance, design, development, and test requirements for the Integrated Timing System, WBS 1.5.3 which is part of the NIF Integrated Computer Control System (ICCS). The Integrated Timing System provides all temporally-critical hardware triggers to components and equipment in other NIF systems

  9. Research on common methods for evaluating the operation effect of integrated wastewater treatment facilities of iron and steel enterprises

    Science.gov (United States)

    Bingsheng, Xu

    2017-04-01

    Considering the large quantities of wastewater generated from iron and steel enterprises in China, this paper is aimed to research the common methods applied for evaluating the integrated wastewater treatment effect of iron and steel enterprises. Based on survey results on environmental protection performance, technological economy, resource & energy consumption, services and management, an indicator system for evaluating the operation effect of integrated wastewater treatment facilities is set up. By discussing the standards and industrial policies in and out of China, 27 key secondary indicators are further defined on the basis of investigation on main equipment and key processes for wastewater treatment, so as to determine the method for setting key quantitative and qualitative indicators for evaluation indicator system. It is also expected to satisfy the basic requirements of reasonable resource allocation, environmental protection and sustainable economic development, further improve the integrated wastewater treatment effect of iron and steel enterprises, and reduce the emission of hazardous substances and environmental impact.

  10. A simulation-based robust biofuel facility location model for an integrated bio-energy logistics network

    Directory of Open Access Journals (Sweden)

    Jae-Dong Hong

    2014-10-01

    Full Text Available Purpose: The purpose of this paper is to propose a simulation-based robust biofuel facility location model for solving an integrated bio-energy logistics network (IBLN problem, where biomass yield is often uncertain or difficult to determine.Design/methodology/approach: The IBLN considered in this paper consists of four different facilities: farm or harvest site (HS, collection facility (CF, biorefinery (BR, and blending station (BS. Authors propose a mixed integer quadratic modeling approach to simultaneously determine the optimal CF and BR locations and corresponding biomass and bio-energy transportation plans. The authors randomly generate biomass yield of each HS and find the optimal locations of CFs and BRs for each generated biomass yield, and select the robust locations of CFs and BRs to show the effects of biomass yield uncertainty on the optimality of CF and BR locations. Case studies using data from the State of South Carolina in the United State are conducted to demonstrate the developed model’s capability to better handle the impact of uncertainty of biomass yield.Findings: The results illustrate that the robust location model for BRs and CFs works very well in terms of the total logistics costs. The proposed model would help decision-makers find the most robust locations for biorefineries and collection facilities, which usually require huge investments, and would assist potential investors in identifying the least cost or important facilities to invest in the biomass and bio-energy industry.Originality/value: An optimal biofuel facility location model is formulated for the case of deterministic biomass yield. To improve the robustness of the model for cases with probabilistic biomass yield, the model is evaluated by a simulation approach using case studies. The proposed model and robustness concept would be a very useful tool that helps potential biofuel investors minimize their investment risk.

  11. Determinants of Integrated Management of Childhood Illness (IMCI) non-severe pneumonia classification and care in Malawi health facilities: Analysis of a national facility census.

    Science.gov (United States)

    Johansson, Emily White; Nsona, Humphreys; Carvajal-Aguirre, Liliana; Amouzou, Agbessi; Hildenwall, Helena

    2017-12-01

    Research shows inadequate Integrated Management of Childhood Illness (IMCI)-pneumonia care in various low-income settings but evidence is largely from small-scale studies with limited evidence of patient-, provider- and facility-levels determinants of IMCI non-severe pneumonia classification and its management. The Malawi Service Provision Assessment 2013-2014 included 3149 outpatients aged 2-59 months with completed observations, interviews and re-examinations. Mixed-effects logistic regression models quantified the influence of patient-, provider and facility-level determinants on having IMCI non-severe pneumonia and its management in observed consultations. Among 3149 eligible outpatients, 590 (18.7%) had IMCI non-severe pneumonia classification in re-examination. 228 (38.7%) classified cases received first-line antibiotics and 159 (26.9%) received no antibiotics. 18.6% with cough or difficult breathing had 60-second respiratory rates counted during consultations, and conducting this assessment was significantly associated with IMCI training ever received (odds ratio (OR) = 2.37, 95% confidence interval (CI): 1.29-4.31) and negative rapid diagnostic test results (OR = 3.21, 95% CI: 1.45-7.13). Older children had lower odds of assessments than infants (OR = 48-59 months: 0.35, 95% CI: 0.16-0.75). Children presenting with any of the following complaints also had reduced odds of assessment: fever, diarrhea, skin problem or any danger sign. First-line antibiotic treatment for classified cases was significantly associated with high temperatures (OR = 3.26, 95% CI: 1.24-8.55) while older children had reduced odds of first-line treatment compared to infants (OR = 48-59 months: 0.29, 95% CI: 0.10-0.83). RDT-confirmed malaria was a significant predictor of no antibiotic receipt for IMCI non-severe pneumonia (OR = 10.65, 95% CI: 2.39-47.36). IMCI non-severe pneumonia care was sub-optimal in Malawi health facilities in 2013-2014 with inadequate

  12. Engineering Evaluation/Cost Analysis for the 100-N Area Ancillary Facilities and Integration Plan

    International Nuclear Information System (INIS)

    Mukherjee, B.

    1997-09-01

    This document presents the results of an engineering evaluation/cost analysis (EE/CA) that was conducted to evaluate alternatives for addressing final disposition of contaminated buildings and structures in the 100-N Area of the Hanford Site. The Hanford Site is located in southeastern Washington State and is owned by the U.S. Government and operated by the U.S. Department of Energy, Richland Operations Office (RL). In November 1989, the 100 Area of the Hanford Site (as well as the 200, 300, and 1100 Areas) was placed on the U.S. Environmental Protection Agency's National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980. The 100 Area NPL includes the 100-N Area, which is in various stages of the remediation process. It has been determined by RL that hazardous substances in the 100-N Area ancillary facilities may present a potential threat to human health or the environment, and that a non-time critical removal action at these facilities is warranted. To help determine the most appropriate action, RL, in cooperation with the Washington State Department of Ecology (Ecology) and the EPA, has prepared this EE/CA. The scope of the evaluation includes the inactive contaminated ancillary facilities in the 100-N Area, the facilities residing in the buffer zone, and the Hanford Generating Plant (HGP) and the solid waste management units (SWMUs) inside HGP support facilities. The 105-N Reactor and 109-N Heat Exchange facilities are excluded from this EE/CA evaluation

  13. Safeguards-by-Design: Early Integration of Physical Protection and Safeguardability into Design of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    T. Bjornard; R. Bean; S. DeMuth; P. Durst; M. Ehinger; M. Golay; D. Hebditch; J. Hockert; J. Morgan

    2009-09-01

    The application of a Safeguards-by-Design (SBD) process for new nuclear facilities has the potential to minimize proliferation and security risks as the use of nuclear energy expands worldwide. This paper defines a generic SBD process and its incorporation from early design phases into existing design / construction processes and develops a framework that can guide its institutionalization. SBD could be a basis for a new international norm and standard process for nuclear facility design. This work is part of the U.S. DOE’s Next Generation Safeguards Initiative (NGSI), and is jointly sponsored by the Offices of Non-proliferation and Nuclear Energy.

  14. The outline of investigation on integrity of JMTR concrete structures, cooling system and utility facilities

    International Nuclear Information System (INIS)

    Ebisawa, Hiroyuki; Hanakawa, Hiroki; Asano, Norikazu; Kusunoki, Hidehiko; Yanai, Tomohiro; Sato, Shinichi; Miyauchi, Masaru; Ohto, Tsutomu; Kimura, Tadashi; Kawamata, Takanori; Nemoto, Nobuaki; Watahiki, Shunsuke; Hanawa, Yoshio; Tsuboi, Kazuaki; Ogasawara, Yasushi; Nemoto, Hiroyoshi; Echigoya, Shinichi; Ohtsuka, Kaoru; Onoue, Ryuji; Koike, Sumio; Gorai, Shigeru; Nishiyama, Yutaka; Kurosawa, Akihiko; Hanawa, Nobuhiro; Tobita, Kenji; Tabata, Shuzo; Fukasaku, Akitomi; Isozaki, Takanori; Akashi, Kazutomo; Takahashi, Kunihiro; Tsuji, Tomoyuki

    2009-07-01

    The condition of facilities and machinery used continuously were investigated before the renewal work of JMTR on FY 2007. The subjects of investigation were reactor building, primary cooling system tanks, secondary cooling system piping and tower, emergency generator and so on. As the result, it was confirmed that some facilities and machinery were necessary to repair and others were used continuously for long term by maintaining on the long-term maintenance plan. JMTR is planed to renew by the result of this investigation. (author)

  15. Discussion of the use of the Dragon reactor as a facility for integral reactor physics experiments

    Energy Technology Data Exchange (ETDEWEB)

    Gutmann, H

    1972-06-05

    The purpose and use of the Dragon Reactor Experiment (DRE) has changed considerably during the years of its operation. The original purpose was to show that the principle of a High Temperature Reactor is sound and demonstrate its operation. After this achievement, the purpose of the Dragon reactor changed to the use as a fuel testing facility. During recent years, a new use of the DRE has been added to its use as a fuel testing facility, namely Fuel Element Design Testing. The current report covers reactor physics experiments aspects.

  16. Integrated O&M for energy generation and exchange facilities; O&M integral para instalaciones de generación e intercambio de energía

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2016-07-01

    Ingeteam Service, part of the Ingeteam Group, is a leading company in the provision of integrated O&M services at energy generation and exchange facilities worldwide. From its head office in the Albacete Science and Technology Park, it manages the work of the 1,300 employees that make up its global workforce, rendering services to wind farms, PV installations and power generation plants. In addition, it maintains an active participation strategy in a range of R&D+i programmes that improve the existing technologies and are geared towards new production systems and new diagnostic techniques, applied to renewables installation maintenance. (Author)

  17. Experimental evaluation of emergency operating procedures on multiple steam generator tube rupture in INER integral system test facility

    International Nuclear Information System (INIS)

    Liu, T.J.; Lin, Y.M.; Lee, C.H.; Chang, C.Y.; Hong, W.T.

    1997-01-01

    The multiple steam generator tube rupture (SGTR) scenario in Westinghouse type pressurized water reactor (PWR) has been investigated at the Institute of Nuclear Energy Research (INER) Integral System Test (IIST) facility. This reduced-height and reduced-pressure test facility was designed to simulate the main features of Maanshan nuclear power plant. The SGTR test scenario assumes the double-ended break of one-, two- and six- tubes without other failures. The major operator actions follow the related symptom-oriented Emergency Operating Procedure (EOP) on the reference plant. This study focuses on the investigation of thermal-hydraulics phenomena and the adequacy of associated EOP to limit primary-to-secondary leakage. Through this study, it is found that the adequacy of current EOP in minimizing the radioactivity release demands early substantial operator involvement, especially in the multi-tubes break events. Also, the detailed mechanism of the main thermal-hydraulic phenomena during the SGTR transient are explored. (author)

  18. National Ignition Facility system design requirements NIF integrated computer controls SDR004

    International Nuclear Information System (INIS)

    Bliss, E.

    1996-01-01

    This System Design Requirement document establishes the performance, design, development, and test requirements for the NIF Integrated Computer Control System. The Integrated Computer Control System (ICCS) is covered in NIF WBS element 1.5. This document responds directly to the requirements detailed in the NIF Functional Requirements/Primary Criteria, and is supported by subsystem design requirements documents for each major ICCS Subsystem

  19. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 1 of 2: Technical standard

    International Nuclear Information System (INIS)

    1998-05-01

    This Department of Energy (DOE) technical standard (referred to as the Standard) provides guidance for integrating and enhancing worker, public, and environmental protection during facility disposition activities. It provides environment, safety, and health (ES and H) guidance to supplement the project management requirements and associated guidelines contained within DOE O 430.1A, Life-Cycle Asset Management (LCAM), and amplified within the corresponding implementation guides. In addition, the Standard is designed to support an Integrated Safety Management System (ISMS), consistent with the guiding principles and core functions contained in DOE P 450.4, Safety Management System Policy, and discussed in DOE G 450.4-1, Integrated Safety Management System Guide. The ISMS guiding principles represent the fundamental policies that guide the safe accomplishment of work and include: (1) line management responsibility for safety; (2) clear roles and responsibilities; (3) competence commensurate with responsibilities; (4) balanced priorities; (5) identification of safety standards and requirements; (6) hazard controls tailored to work being performed; and (7) operations authorization. This Standard specifically addresses the implementation of the above ISMS principles four through seven, as applied to facility disposition activities

  20. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 2: Appendices

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-05-01

    This volume contains the appendices that provide additional environment, safety, and health (ES and H) information to complement Volume 1 of this Standard. Appendix A provides a set of candidate DOE ES and H directives and external regulations, organized by hazard types that may be used to identify potentially applicable directives to a specific facility disposition activity. Appendix B offers examples and lessons learned that illustrate implementation of ES and H approaches discussed in Section 3 of Volume 1. Appendix C contains ISMS performance expectations to guide a project team in developing and implementing an effective ISMS and in developing specific performance criteria for use in facility disposition. Appendix D provides guidance for identifying potential Applicable or Relevant and Appropriate Requirements (ARARs) when decommissioning facilities fall under the Comprehensive Environmental Response, Compensation, Liability Act (CERCLA) process. Appendix E discusses ES and H considerations for dispositioning facilities by privatization. Appendix F is an overview of the WSS process. Appendix G provides a copy of two DOE Office of Nuclear Safety Policy and Standards memoranda that form the bases for some of the guidance discussed within the Standard. Appendix H gives information on available hazard analysis techniques and references. Appendix I provides a supplemental discussion to Sections 3.3.4, Hazard Baseline Documentation, and 3.3.6, Environmental Permits. Appendix J presents a sample readiness evaluation checklist.

  1. Integrated Urban Flood Analysis considering Optimal Operation of Flood Control Facilities in Urban Drainage Networks

    Science.gov (United States)

    Moon, Y. I.; Kim, M. S.; Choi, J. H.; Yuk, G. M.

    2017-12-01

    eavy rainfall has become a recent major cause of urban area flooding due to the climate change and urbanization. To prevent property damage along with casualties, a system which can alert and forecast urban flooding must be developed. Optimal performance of reducing flood damage can be expected of urban drainage facilities when operated in smaller rainfall events over extreme ones. Thus, the purpose of this study is to execute: A) flood forecasting system using runoff analysis based on short term rainfall; and B) flood warning system which operates based on the data from pump stations and rainwater storage in urban basins. In result of the analysis, it is shown that urban drainage facilities using short term rainfall forecasting data by radar will be more effective to reduce urban flood damage than using only the inflow data of the facility. Keywords: Heavy Rainfall, Urban Flood, Short-term Rainfall Forecasting, Optimal operating of urban drainage facilities. AcknowledgmentsThis research was supported by a grant (17AWMP-B066744-05) from Advanced Water Management Research Program (AWMP) funded by Ministry of Land, Infrastructure and Transport of Korean government.

  2. COMPLETION OF THE FIRST INTEGRATED SPENT NUCLEAR FUEL TRANSSHIPMENT/INTERIM STORAGE FACILITY IN NW RUSSIA

    International Nuclear Information System (INIS)

    Dyer, R.S.; Barnes, E.; Snipes, R.L.; Hoeibraaten, S.; Gran, H.C.; Foshaug, E.; Godunov, V.

    2003-01-01

    Northwest and Far East Russia contain large quantities of unsecured spent nuclear fuel (SNF) from decommissioned submarines that potentially threaten the fragile environments of the surrounding Arctic and North Pacific regions. The majority of the SNF from the Russian Navy, including that from decommissioned nuclear submarines, is currently stored in on-shore and floating storage facilities. Some of the SNF is damaged and stored in an unstable condition. Existing Russian transport infrastructure and reprocessing facilities cannot meet the requirements for moving and reprocessing this amount of fuel. Additional interim storage capacity is required. Most of the existing storage facilities being used in Northwest Russia do not meet health and safety, and physical security requirements. The United States and Norway are currently providing assistance to the Russian Federation (RF) in developing systems for managing these wastes. If these wastes are not properly managed, they could release significant concentrations of radioactivity to these sensitive environments and could become serious global environmental and physical security issues. There are currently three closely-linked trilateral cooperative projects: development of a prototype dual-purpose transport and storage cask for SNF, a cask transshipment interim storage facility, and a fuel drying and cask de-watering system. The prototype cask has been fabricated, successfully tested, and certified. Serial production is now underway in Russia. In addition, the U.S. and Russia are working together to improve the management strategy for nuclear submarine reactor compartments after SNF removal

  3. Field Research Facility Data Integration Framework Data Management Plan: Survey Lines Dataset

    Science.gov (United States)

    2016-08-01

    Geographic Information System ERDC/CHL SR-16-4 viii GPS global positioning system ID identification ISO International Organization for...Time Kinematic Global Positioning System SDSFIE Spatial Data Standards for Facilities, Infrastructure, and Environment TOPO topographic TSS...Resupply Cargo V (LARC-V) vessel which is capable of continuous data collection from the beach, through the surf zone, and offshore. Conductivity

  4. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 2: Appendices

    International Nuclear Information System (INIS)

    1998-05-01

    This volume contains the appendices that provide additional environment, safety, and health (ES and H) information to complement Volume 1 of this Standard. Appendix A provides a set of candidate DOE ES and H directives and external regulations, organized by hazard types that may be used to identify potentially applicable directives to a specific facility disposition activity. Appendix B offers examples and lessons learned that illustrate implementation of ES and H approaches discussed in Section 3 of Volume 1. Appendix C contains ISMS performance expectations to guide a project team in developing and implementing an effective ISMS and in developing specific performance criteria for use in facility disposition. Appendix D provides guidance for identifying potential Applicable or Relevant and Appropriate Requirements (ARARs) when decommissioning facilities fall under the Comprehensive Environmental Response, Compensation, Liability Act (CERCLA) process. Appendix E discusses ES and H considerations for dispositioning facilities by privatization. Appendix F is an overview of the WSS process. Appendix G provides a copy of two DOE Office of Nuclear Safety Policy and Standards memoranda that form the bases for some of the guidance discussed within the Standard. Appendix H gives information on available hazard analysis techniques and references. Appendix I provides a supplemental discussion to Sections 3.3.4, Hazard Baseline Documentation, and 3.3.6, Environmental Permits. Appendix J presents a sample readiness evaluation checklist

  5. Development of a model forecasting Dermanyssus gallinae's population dynamics for advancing Integrated Pest Management in laying hen facilities.

    Science.gov (United States)

    Mul, Monique F; van Riel, Johan W; Roy, Lise; Zoons, Johan; André, Geert; George, David R; Meerburg, Bastiaan G; Dicke, Marcel; van Mourik, Simon; Groot Koerkamp, Peter W G

    2017-10-15

    The poultry red mite, Dermanyssus gallinae, is the most significant pest of egg laying hens in many parts of the world. Control of D. gallinae could be greatly improved with advanced Integrated Pest Management (IPM) for D. gallinae in laying hen facilities. The development of a model forecasting the pests' population dynamics in laying hen facilities without and post-treatment will contribute to this advanced IPM and could consequently improve implementation of IPM by farmers. The current work describes the development and demonstration of a model which can follow and forecast the population dynamics of D. gallinae in laying hen facilities given the variation of the population growth of D. gallinae within and between flocks. This high variation could partly be explained by house temperature, flock age, treatment, and hen house. The total population growth variation within and between flocks, however, was in part explained by temporal variation. For a substantial part this variation was unexplained. A dynamic adaptive model (DAP) was consequently developed, as models of this type are able to handle such temporal variations. The developed DAP model can forecast the population dynamics of D. gallinae, requiring only current flock population monitoring data, temperature data and information of the dates of any D. gallinae treatment. Importantly, the DAP model forecasted treatment effects, while compensating for location and time specific interactions, handling the variability of these parameters. The characteristics of this DAP model, and its compatibility with different mite monitoring methods, represent progression from existing approaches for forecasting D. gallinae that could contribute to advancing improved Integrated Pest Management (IPM) for D. gallinae in laying hen facilities. Copyright © 2017 Elsevier B.V. All rights reserved.

  6. Integration of Hardware-in-the-loop Facilities Over the Internet

    Science.gov (United States)

    2009-04-15

    This briefing discusses a hardware in loop vehicle simulator in Warren, Michigan that provides the driver with realistic power response from the Power and Energy Systems Integration Lab over the internet.

  7. CyberCIEGE Scenario Illustrating Integrity Risks to a Military-Like Facility

    National Research Council Canada - National Science Library

    Fielk, Klaus

    2004-01-01

    .... This thesis asked if a Scenario Definition File (SDF) for the CyberCIEGE game could be developed to educate and train players in Information Assurance on matters related to information integrity in a networking environment...

  8. Development of high integrity, maximum durability concrete structures for LLW disposal facilities

    International Nuclear Information System (INIS)

    Taylor, W.P.

    1992-01-01

    A number of disposal facilities for Low-Level Radioactive Wastes have been planned for the Savannah River Site. Design has been completed for disposal vaults for several waste classifications and construction is nearly complete or well underway on some facilities. Specific design criteria varies somewhat for each waste classification. All disposal units have been designed as below-grade concrete vaults, although the majority will be above ground for many years before being encapsulated with earth at final closure. Some classes of vaults have a minimum required service life of 100 years. All vaults utilize a unique blend of cement, blast furnace slag and pozzolan. The design synthesizes the properties of the concrete mix with carefully planned design details and construction methodologies to (1) eliminate uncontrolled cracking; (2) minimize leakage potential; and (3) maximize durability. The first of these vaults will become operational in 1992. 9 refs

  9. Royal Military College of Canada SLOWPOKE-2 facility. Integrated regulating and instrumentation system (SIRCIS) upgrade project

    International Nuclear Information System (INIS)

    Corcoran, W.P.; Nielsen, K.S.; Kelly, D.G.; Weir, R.D.

    2013-01-01

    The SLOWPOKE-2 Facility at the Royal Military College of Canada has operated the only digitally controlled SLOWPOKE reactor since 2001 (Version 1.0). The present work describes ongoing project development to provide a robust digital reactor control system that is consistent with Aging Management as summarized in the Facility's Life Cycle Management and Maintenance Plan. The project has transitioned from a post-graduate research activity to a comprehensively managed project supported by a team of RMCC professional and technical staff who have delivered an update of the V1.1 system software and hardware implementation that is consistent with best Canadian nuclear industry practice. The challenges associated with the implementation of Version 2.0 in February 2012, the lessons learned from this implementation, and the applications of these lessons to a redesign and rewrite of the RMCC SLOWPOKE-2 digital instrumentation and regulating system (Version 3) are discussed. (author)

  10. An Integrated Approach for Reliable Facility Location/Network Design Problem with Link Disruption

    Directory of Open Access Journals (Sweden)

    Davood Shishebori

    2015-05-01

    Full Text Available Proposing a robust designed facility location is one of the most effective ways to hedge against unexpected disruptions and failures in a transportation network system. This paper considers the combined facility location/network design problem with regard to transportation link disruptions and develops a mixed integer linear programming formulation to model it. With respect to the probability of link disruptions, the objective function of the model minimizes the total costs, including location costs, link construction costs and also the expected transportation costs. An efficient hybrid algorithm based on LP relaxation and variable neighbourhood search metaheuristic is developed in order to solve the mathematical model. Numerical results demonstrate that the proposed hybrid algorithm has suitable efficiency in terms of duration of solution time and determining excellent solution quality.

  11. Integral high energy nuclon-nucleus cross sections for mathematical experiments with electronuclear facilities

    International Nuclear Information System (INIS)

    Barashenkov, V.S.; Gudowski, W.; Polanski, A.

    1999-01-01

    A parametrization of the integral cross sections σ nonel , σ tl , σ tot for the elastic nonelastic and total proton- and neutron-nucleus interactions is considered at medium and high energies. On the basis of this parametrization a code is created for the interpolational calculations of the integral cross sections for arbitrary target nuclei at proton energies E=1 MeV - 1 TeV and neutron energies E=12.5 MeV - 1 TeV

  12. The role of integrated logistic support in performance assessment of nuclear facilities

    International Nuclear Information System (INIS)

    Prager, G.; Munro, J.F.

    1988-01-01

    Integrated logistic support (ILS) is a process used extensively by the Department of Defense as the major tool for weapons systems readiness and support-ability. ILS provides a proven scientific and engineering method for defining system support requirements while acquiring necessary support. ILS is also the management process for planning, programming and integrating support-ability considerations into the acquisition and operations process. Concurrent with the acquisition of material support requirements are identified, planned, evaluated, acquired and installed

  13. Technical feasibility of an Integral Fast Reactor (IFR) as a future option for fast reactor cycles. Integrate a small metal-fueled fast reactor and pyroprocessing facilities

    International Nuclear Information System (INIS)

    Tanaka, Nobuo

    2017-01-01

    Integral Fast Reactor that integrated fast reactor and pyrorocessing facilities developed by Argonne National Laboratory in the U.S. is an excellent nuclear fuel cycle system for passive safety, nuclear non-proliferation, and reduction in radioactive waste. In addition, this system can be considered as a technology applicable to the treatment of the fuel debris caused by the Fukushima Daiichi Nuclear Power Station accident. This study assessed the time required for debris processing, safety of the facilities, and construction cost when using this technology, and examined technological possibility including future technological issues. In a small metal-fueled reactor, it is important to design the core that achieves both of reduction in combustion reactivity and reduction in coolant reactivity. In system design, calorimetric analysis, structure soundness assessment, seismic feasibility establishment study, etc. are important. Regarding safety, research and testing are necessary on the capabilities of passive reactor shutdown and reactor core cooling as well as measures for avoiding re-criticality, even when emergency stop has failed. In dry reprocessing system, studies on electrolytic reduction and electrolytic refining process for treating the debris with compositions different from those of normal fuel are necessary. (A.O.)

  14. Insight into implementation of facility-based integrated management of childhood illness strategy in a rural district of Sindh, Pakistan.

    Science.gov (United States)

    Pradhan, Nousheen Akber; Rizvi, Narjis; Sami, Neelofar; Gul, Xaher

    2013-07-05

    Integrated management of childhood illnesses (IMCI) strategy has been proven to improve health outcomes in children under 5 years of age. Pakistan, despite being in the late implementation phase of the strategy, continues to report high under-five mortality due to pneumonia, diarrhea, measles, and malnutrition - the main targets of the strategy. The study determines the factors influencing IMCI implementation at public-sector primary health care (PHC) facilities in Matiari district, Sindh, Pakistan. An exploratory qualitative study with an embedded quantitative strand was conducted. The qualitative part included 16 in-depth interviews (IDIs) with stakeholders which included planners and policy makers at a provincial level (n=5), implementers and managers at a district level (n=3), and IMCI-trained physicians posted at PHC facilities (n=8). Quantitative part included PHC facility survey (n=16) utilizing WHO health facility assessment tool to assess availability of IMCI essential drugs, supplies, and equipments. Qualitative content analysis was used to interpret the textual information, whereas descriptive frequencies were calculated for health facility survey data. The major factors reported to enhance IMCI implementation were knowledge and perception about the strategy and need for separate clinic for children aged under 5 years as potential support factors. The latter can facilitate in strategy implementation through allocated workforce and required equipments and supplies. Constraint factors mainly included lack of clear understanding of the strategy, poor planning for IMCI implementation, ambiguity in defined roles and responsibilities among stakeholders, and insufficient essential supplies and drugs at PHC centers. The latter was further substantiated through health facilities' survey findings, which indicated that none of the facilities had 100% stock of essential supplies and drugs. Only one out of all 16 surveyed facilities had 75% of the total supplies

  15. Developing Mobile- and BIM-Based Integrated Visual Facility Maintenance Management System

    Directory of Open Access Journals (Sweden)

    Yu-Cheng Lin

    2013-01-01

    Full Text Available Facility maintenance management (FMM has become an important topic for research on the operation phase of the construction life cycle. Managing FMM effectively is extremely difficult owing to various factors and environments. One of the difficulties is the performance of 2D graphics when depicting maintenance service. Building information modeling (BIM uses precise geometry and relevant data to support the maintenance service of facilities depicted in 3D object-oriented CAD. This paper proposes a new and practical methodology with application to FMM using BIM technology. Using BIM technology, this study proposes a BIM-based facility maintenance management (BIMFMM system for maintenance staff in the operation and maintenance phase. The BIMFMM system is then applied in selected case study of a commercial building project in Taiwan to verify the proposed methodology and demonstrate its effectiveness in FMM practice. Using the BIMFMM system, maintenance staff can access and review 3D BIM models for updating related maintenance records in a digital format. Moreover, this study presents a generic system architecture and its implementation. The combined results demonstrate that a BIMFMM-like system can be an effective visual FMM tool.

  16. PMK-2 the Hungarian integral type test facility. Documentations, publications and archivations of experiments

    International Nuclear Information System (INIS)

    Perneczky, L.; Guba, A.; Ezsoel, G.; Toth, I.; Szabados, L.

    2002-01-01

    The PMK-2 experimental facility at the KFKI-AEKI, Budapest, is a full pressure, scaled down model of the primary and partly the secondary circuit of the Paks NPP, which is equipped with four VVER-440/213-type reactors. Since the start-up of the facility altogether 48 experiments have been performed for groups of transients as follows: one- and two-phase natural circulation, loss of coolant accidents, special plant transients and experiments in support of accident management procedures. The results have been used for the validation of thermal-hydraulic system codes for VVER applications. Following the experiments a detailed documentation and archiving activity - using an optimised data storage - was required to preserve the essential information and to assure these for a widely utilisation for the international nuclear community. In the publication list related to the facility and the experiments for the moment altogether 280 items - documents, articles in periodicals, papers in proceedings and research reports - in six languages were collected. The paper gives an overview on this activity including the participation in the EU CERTA-TN programme, where AEKI introduced representative databases of two PMK-2 tests in the STRESA Network.(author)

  17. Integrated Corrosion Facility for long-term testing of candidate materials for high-level radioactive waste containment

    International Nuclear Information System (INIS)

    Estill, J.C.; Dalder, E.N.C.; Gdowski, G.E.; McCright, R.D.

    1994-10-01

    A long-term-testing facility, the Integrated Corrosion Facility (I.C.F.), is being developed to investigate the corrosion behavior of candidate construction materials for high-level-radioactive waste packages for the potential repository at Yucca Mountain, Nevada. Corrosion phenomena will be characterized in environments considered possible under various scenarios of water contact with the waste packages. The testing of the materials will be conducted both in the liquid and high humidity vapor phases at 60 and 90 degrees C. Three classes of materials with different degrees of corrosion resistance will be investigated in order to encompass the various design configurations of waste packages. The facility is expected to be in operation for a minimum of five years, and operation could be extended to longer times if warranted. A sufficient number of specimens will be emplaced in the test environments so that some can be removed and characterized periodically. The corrosion phenomena to be characterized are general, localized, galvanic, and stress corrosion cracking. The long-term data obtained from this study will be used in corrosion mechanism modeling, performance assessment, and waste package design. Three classes of materials are under consideration. The corrosion resistant materials are high-nickel alloys and titanium alloys; the corrosion allowance materials are low-alloy and carbon steels; and the intermediate corrosion resistant materials are copper-nickel alloys

  18. An application of the value tree analysis methodology within the integrated risk informed decision making for the nuclear facilities

    International Nuclear Information System (INIS)

    Borysiewicz, Mieczysław; Kowal, Karol; Potempski, Sławomir

    2015-01-01

    A new framework of integrated risk informed decision making (IRIDM) has been recently developed in order to improve the risk management of the nuclear facilities. IRIDM is a process in which qualitatively different inputs, corresponding to different types of risk, are jointly taken into account. However, the relative importance of the IRIDM inputs and their influence on the decision to be made is difficult to be determined quantitatively. An improvement of this situation can be achieved by application of the Value Tree Analysis (VTA) methods. The aim of this article is to present the VTA methodology in the context of its potential usage in the decision making on nuclear facilities. The benefits of the VTA application within the IRIDM process were identified while making the decision on fuel conversion of the research reactor MARIA. - Highlights: • New approach to risk informed decision making on nuclear facilities was postulated. • Value tree diagram was developed for decision processes on nuclear installations. • An experiment was performed to compare the new approach with the standard one. • Benefits of the new approach were reached in fuel conversion of a research reactor. • The new approach makes the decision making process more transparent and auditable

  19. Insight into implementation of facility-based integrated management of childhood illness strategy in a rural district of Sindh, Pakistan

    Directory of Open Access Journals (Sweden)

    Nousheen Akber Pradhan

    2013-07-01

    Full Text Available Background: Integrated management of childhood illnesses (IMCI strategy has been proven to improve health outcomes in children under 5 years of age. Pakistan, despite being in the late implementation phase of the strategy, continues to report high under-five mortality due to pneumonia, diarrhea, measles, and malnutrition – the main targets of the strategy. Objective: The study determines the factors influencing IMCI implementation at public-sector primary health care (PHC facilities in Matiari district, Sindh, Pakistan. Design: An exploratory qualitative study with an embedded quantitative strand was conducted. The qualitative part included 16 in-depth interviews (IDIs with stakeholders which included planners and policy makers at a provincial level (n=5, implementers and managers at a district level (n=3, and IMCI-trained physicians posted at PHC facilities (n=8. Quantitative part included PHC facility survey (n=16 utilizing WHO health facility assessment tool to assess availability of IMCI essential drugs, supplies, and equipments. Qualitative content analysis was used to interpret the textual information, whereas descriptive frequencies were calculated for health facility survey data. Results: The major factors reported to enhance IMCI implementation were knowledge and perception about the strategy and need for separate clinic for children aged under 5 years as potential support factors. The latter can facilitate in strategy implementation through allocated workforce and required equipments and supplies. Constraint factors mainly included lack of clear understanding of the strategy, poor planning for IMCI implementation, ambiguity in defined roles and responsibilities among stakeholders, and insufficient essential supplies and drugs at PHC centers. The latter was further substantiated through health facilities’ survey findings, which indicated that none of the facilities had 100% stock of essential supplies and drugs. Only one out of all

  20. ISO 9001 and ISO 14001: An Integrated Quality Management System for an MTR Facility SAFARI-1 Research Reactor

    International Nuclear Information System (INIS)

    Du Bruyn, J.F.; Piani, C.S.B.

    2005-01-01

    The SAFARI-1 research reactor, owned and operated by the South African Nuclear Energy Corporation (Necsa), initially obtained ISO 9001 accreditation of its Quality, Health, Safety and Environmental (QHSE) management system via international affiliation from the South African Bureau of Standards (SABS) during 1998 and re-certification according to ISO 9001 (2000) in 2003. With ever-increasing demands on nuclear facilities to demonstrate conformance to environmental policies, SAFARI-1 has now developed an Environmental Management System (EMS) that is compliant with ISO 14001 (1996) and is fully integrated with the SAFARI-1 Quality Management System (QMS). The dynamic involvement of SAFARI-1 in commercial applications demanded that any transition of the original QMS to a fully incorporated QHSE system had to be done in a way that would ensure sustained delivery of a safe and reliable service with continuous quality. At the same time, the primary vision of operating a facility under an efficient financial management programme was essential. The criteria established by the original ISO 9001 compliant QMS were appraised against the additional requirements of ISO 14001 and a suitable superstructure derived for generation and implementation of an inclusive EMS. The transitional integration of this system was planned so as to produce a QMS suitable to quality, environmental and other management related issues for application to the unique function of a nuclear research reactor. (author)

  1. Integrated operations plan for the MFTF-B Mirror Fusion Test Facility. Volume I. Organization plan

    International Nuclear Information System (INIS)

    1981-12-01

    This plan and the accompanying MFTF-B Integrated Operations Plan are submitted in response to UC/LLNL Purchase Order 3883801, dated July 1981. The organization plan also addresses the specific tasks and trade studies directed by the scope of work. The Integrated Operations Plan, which includes a reliability, quality assurance, and safety plan and an integrated logistics plan, comprises the burden of the report. In the first section of this volume, certain underlying assumptions and observations are discussed setting the requirements and limits for organization. Section B presents the recommended structure itself. Section C Device Availability vs Maintenance and Support Efforts and Section D Staffing Levels and Skills provide backup detail and justification. Section E is a trade study on maintenance and support by LLNL staff vs subcontract and Section F is a plan for transitioning from the construction phase into operation. A brief summary of schedules and estimated costs concludes the volume

  2. Fire protection system management in nuclear facilities: strengthening factor of integrated management system - a case study

    International Nuclear Information System (INIS)

    Santos, Joao Regis dos

    2005-01-01

    The present study investigated and analyzed the importance of a system of integrated safety manage, environment and health in a nuclear installation, having as perspective, the fire protection manage. The inquiry was made using a qualitative research involving a case study, where the considered environment was the Reconversion and UO 2 Plant of the Industrias Nucleares do Brasil (INB), located in Resende, Rio de Janeiro and the studied population, the managers and the staff directly involved with the aspects related to the safety of the industrial complex of the related company. The motivation for the research was the search of a bigger interaction of the questions related to the safety, environment and health in the nuclear industry having, as axle of the investigation, the fire protection. As a result, it was observed that in a nuclear installation, although dealing with diversified safety processes, integration is possible and necessary, since there are more reasons for integration than otherwise. (author)

  3. Heat treatment of nuclear reactor pump part in integrated furnace facility

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    A flexible heat treating system is meeting strict work specifications while accommodating the production flow pattern requirements and floor space needs of Advanced Metal Treating, Inc., Butler, Wis. Modular design and appropriate furnace configurations allow realization of the most efficient heat treat processing and energy use in a relatively small production area. The totally-integrated system (Pacemaker--manufactured by Lindberg, A Unit of General Signal, Chicago) consists of an electric integral-quench furnace with companion draw furnaces, washer unit and a material transfer car. With its one-side, inout configuration, the furnace operates with a minimum of drawing and washing equipment. The integral-quench furnace has a work chamber dimension of 30 by 48 by 30 inches (76.2 x 122 x 76.2 cm). The firm has two of these units, plus three in-out draw furnaces, one washer, one transfer car and two endothermic gas generators

  4. Facility Registry Service (FRS)

    Data.gov (United States)

    U.S. Environmental Protection Agency — The Facility Registry Service (FRS) provides an integrated source of comprehensive (air, water, and waste) environmental information about facilities across EPA,...

  5. Integrating innovative technology into remedial action at a US Department of Energy facility

    International Nuclear Information System (INIS)

    Diggs, I.W.

    1992-01-01

    The US Atomic Energy Commission (AEC), predecessor to the US Department Energy (DOE), established a production complex in the early 1950's for processing uranium and its compounds from natural uranium ore concentrates for the purpose of producing high purity uranium metal for various uses in defense reactor and nuclear weapons programs. This complex, previously known as the Feed Materials Production Center (FMPC), is now known as the Fernald Environmental Management Project (FEMP). In 1989, production was stopped at the feed materials facility due to a decision by the DOE. In December of 1989, the site was placed on the US EPA's National Priorities List (NPL) of sites requiring environmental cleanup. As a result, in April of 1990 the DOE and the US EPA signed a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Consent Agreement which augmented the FFCA. The DOE recently decided that production at the facility would not be resumed, and therefore, the main scope of work would change to remediation and closure of the site. In response to the FFCA and consistent with the modifications agreed to in the amended Consent Agreement, a Remedial Investigation/Feasibility Study (RI/FS) is in progress pursuant to CERCLA, as amended by the Superfund Amendments and Reauthorization Act (SARA). A RI/FS is a comprehensive environmental investigation systematically conducted according to US EPA regulations and guidelines used to identify and select an action plan for the cleanup of CERCLA sites. The RI phase incorporates a broad-based study to evaluate as completely as possible existing environmental and public health risks associated with past or existing facility operations. The FS phase develops and evaluates corrective action alternatives to mitigate identified environmental concerns

  6. Health risks for the population living in the vicinity of an Integrated Waste Management Facility: Screening environmental pollutants

    International Nuclear Information System (INIS)

    Domingo, José L.; Rovira, Joaquim; Vilavert, Lolita; Nadal, Martí; Figueras, María J.; Schuhmacher, Marta

    2015-01-01

    We performed a screening investigation to assess the human health risks of the Integrated Waste Management Facility (IWMF: mechanical–biological treatment (MBT) plant plus municipal solid waste incinerator (MSWI); Ecoparc-3) of Barcelona (Spain). Air concentrations of pollutants potentially released by the MBT plant (VOCs and bioaerosols) and the MSWI (trace elements, PCDD/Fs and PCBs) were determined. Trace elements, PCDD/Fs and PCBs were also analyzed in soil samples. The concentrations of trace elements and bioaerosols were similar to those previously reported in other areas of similar characteristics, while formaldehyde was the predominant VOC. Interestingly, PCDD/F concentrations in soil and air were the highest ever reported near a MSWI in Catalonia, being maximum concentrations 10.8 ng WHO-TEQ/kg and 41.3 fg WHO-TEQ/m 3 , respectively. In addition, there has not been any reduction in soils, even after the closure of a power plant located adjacently. Human health risks of PCDD/F exposure in the closest urban nucleus located downwind the MSWI are up to 10-times higher than those nearby other MSWIs in Catalonia. Although results must be considered as very preliminary, they are a serious warning for local authorities. We strongly recommend to conduct additional studies to confirm these findings and, if necessary, to implement measures to urgently mitigate the impact of the MSWI on the surrounding environment. We must also state the tremendous importance of an individual evaluation of MSWIs, rather than generalizing their environmental and health risks. - Highlights: • Health risks of an Integrated Waste Management Facility in Catalonia are assessed. • PCDD/F exposure near this facility is up to 10-times higher than that near others. • Environmental monitoring of incineration plants should be performed case-by-case. • Since results are very preliminary, confirmatory studies should be conducted

  7. Health risks for the population living in the vicinity of an Integrated Waste Management Facility: Screening environmental pollutants

    Energy Technology Data Exchange (ETDEWEB)

    Domingo, José L., E-mail: joseluis.domingo@urv.cat [Laboratory of Toxicology and Environmental Health, School of Medicine, IISPV, Universitat Rovira i Virgili, Sant Llorenç 21, 43201 Reus, Catalonia (Spain); Rovira, Joaquim [Laboratory of Toxicology and Environmental Health, School of Medicine, IISPV, Universitat Rovira i Virgili, Sant Llorenç 21, 43201 Reus, Catalonia (Spain); Departament d' Enginyeria Quimica, Universitat Rovira i Virgili, Av. Països Catalans 26, 43007 Tarragona, Catalonia (Spain); Vilavert, Lolita; Nadal, Martí [Laboratory of Toxicology and Environmental Health, School of Medicine, IISPV, Universitat Rovira i Virgili, Sant Llorenç 21, 43201 Reus, Catalonia (Spain); Figueras, María J. [Microbiology Unit, School of Medicine, Universitat Rovira i Virgili, Sant Llorenç 21, 43201 Reus, Catalonia (Spain); Schuhmacher, Marta [Laboratory of Toxicology and Environmental Health, School of Medicine, IISPV, Universitat Rovira i Virgili, Sant Llorenç 21, 43201 Reus, Catalonia (Spain); Departament d' Enginyeria Quimica, Universitat Rovira i Virgili, Av. Països Catalans 26, 43007 Tarragona, Catalonia (Spain)

    2015-06-15

    We performed a screening investigation to assess the human health risks of the Integrated Waste Management Facility (IWMF: mechanical–biological treatment (MBT) plant plus municipal solid waste incinerator (MSWI); Ecoparc-3) of Barcelona (Spain). Air concentrations of pollutants potentially released by the MBT plant (VOCs and bioaerosols) and the MSWI (trace elements, PCDD/Fs and PCBs) were determined. Trace elements, PCDD/Fs and PCBs were also analyzed in soil samples. The concentrations of trace elements and bioaerosols were similar to those previously reported in other areas of similar characteristics, while formaldehyde was the predominant VOC. Interestingly, PCDD/F concentrations in soil and air were the highest ever reported near a MSWI in Catalonia, being maximum concentrations 10.8 ng WHO-TEQ/kg and 41.3 fg WHO-TEQ/m{sup 3}, respectively. In addition, there has not been any reduction in soils, even after the closure of a power plant located adjacently. Human health risks of PCDD/F exposure in the closest urban nucleus located downwind the MSWI are up to 10-times higher than those nearby other MSWIs in Catalonia. Although results must be considered as very preliminary, they are a serious warning for local authorities. We strongly recommend to conduct additional studies to confirm these findings and, if necessary, to implement measures to urgently mitigate the impact of the MSWI on the surrounding environment. We must also state the tremendous importance of an individual evaluation of MSWIs, rather than generalizing their environmental and health risks. - Highlights: • Health risks of an Integrated Waste Management Facility in Catalonia are assessed. • PCDD/F exposure near this facility is up to 10-times higher than that near others. • Environmental monitoring of incineration plants should be performed case-by-case. • Since results are very preliminary, confirmatory studies should be conducted.

  8. Integration, design, and construction of a CELSS breadboard facility for bioregenerative life support system research

    Science.gov (United States)

    Prince, R.; Knott, W.; Buchanan, Paul

    1987-01-01

    Design criteria for the Biomass Production Chamber (BPC), preliminary operating procedures, and requirements for the future development of the Controlled Ecological Life Support System (CELSS) are discussed. CELSS, which uses a bioregenerative system, includes the following three major units: (1) a biomass production component to grow plants under controlled conditions; (2) food processing components to derive maximum edible content from all plant parts; and (3) waste management components to recover and recycle all solids, liquids, and gases necessary to support life. The current status of the CELSS breadboard facility is reviewed; a block diagram of a simplified version of CELSS and schematic diagrams of the BPS are included.

  9. Integrated assessment of a new Waste-to-Energy facility in Central Greece in the context of regional perspectives

    International Nuclear Information System (INIS)

    Perkoulidis, G.; Papageorgiou, A.; Karagiannidis, A.; Kalogirou, S.

    2010-01-01

    The main aim of this study is the integrated assessment of a proposed Waste-to-Energy facility that could contribute in the Municipal Solid Waste Management system of the Region of Central Greece. In the context of this paper alternative transfer schemes for supplying the candidate facility were assessed considering local conditions and economical criteria. A mixed-integer linear programming model was applied for the determination of optimum locations of Transfer Stations for an efficient supplying chain between the waste producers and the Waste-to-Energy facility. Moreover different Regional Waste Management Scenarios were assessed against multiple criteria, via the Multi Criteria Decision Making method ELECTRE III. The chosen criteria were total cost, Biodegradable Municipal Waste diversion from landfill, energy recovery and Greenhouse Gas emissions and the analysis demonstrated that a Waste Management Scenario based on a Waste-to-Energy plant with an adjacent landfill for disposal of the residues would be the best performing option for the Region, depending however on the priorities of the decision makers. In addition the study demonstrated that efficient planning is necessary and the case of three sanitary landfills operating in parallel with the WtE plant in the study area should be avoided. Moreover alternative cases of energy recovery of the candidate Waste-to-Energy facility were evaluated against the requirements of the new European Commission Directive on waste in order for the facility to be recognized as recovery operation. The latter issue is of high significance and the decision makers in European Union countries should take it into account from now on, in order to plan and implement facilities that recover energy efficiently. Finally a sensitivity check was performed in order to evaluate the effects of increased recycling rate, on the calorific value of treated Municipal Solid Waste and the gate fee of the candidate plant and found that increased

  10. Doing your own time: Peer integration, aggression and mental health in Dutch male detainment facilities

    NARCIS (Netherlands)

    Kreager, Derek A.; Palmen, Hanneke; Dirkzwager, Anja J.e.; Nieuwbeerta, Paul

    2016-01-01

    Background Prior research demonstrates a strong positive association between social integration (e.g., strong social ties) and individual health. However, researchers also emphasize that this correlation may vary by context and potentially reverse direction under certain conditions. In this study,

  11. Integration and Assessment of Multiple Mobile Manipulators in a Real-World Industrial Production Facility

    DEFF Research Database (Denmark)

    Bøgh, Simon; Schou, Casper; Rühr, Thomas

    2014-01-01

    This paper presents a large-scale research experiment carried out within the TAPAS project, where multiple mobile manipulators were integrated and assessed in an industrial context. We consider an industrial scenario in which mobile manipulators naturally extend automation of logistic tasks towar...

  12. Advancing Integrated Pest Management for Dermanyssus gallinae in laying hen facilities

    NARCIS (Netherlands)

    Mul, Monique F.

    2017-01-01

    Pest and diseases in agricultural systems reduce the yield and quality of available food and feed worldwide. To meet the global growing demand for these products, losses should be reduced, preferably in a sustainable way. Integrated Pest Management (IPM) is a

  13. Potential of roof-integrated solar collectors for preheating air at drying facilities in Northern Thailand

    Energy Technology Data Exchange (ETDEWEB)

    Roman, Franz; Nagle, Marcus; Leis, Hermann; Mueller, Joachim [Institute of Agricultural Engineering 440e, University of Hohenheim, Garbenstrasse 9, 70599 Stuttgart (Germany); Janjai, Serm [Department of Physics, Silpakorn University, Nakhon Pathom (Thailand); Mahayothee, Busarakorn [Department of Food Technology, Silpakorn University, Nakhon Pathom (Thailand); Haewsungcharoen, Methinee [Department of Food Engineering, Chiang Mai University, Chiang Mai (Thailand)

    2009-07-15

    Longan is one of the most widely cropped fruits in Northern Thailand, where a significant amount of the annual harvest is commercially dried and exported as a commodity. Liquefied petroleum gas is generally used as the energy source for heating the drying air, but concern is growing as fuel prices are expected to increase for the foreseeable future. Meanwhile, with the ample solar radiation in Thailand, the roofs of drying facilities could be adapted to serve as solar collectors to preheat the drying air, thus reducing the energy requirement from fossil fuels. In this study, a simulation program for a flat-plate solar air heater was used to estimate the potential to preheat drying air given the conditions of several longan drying facilities. Results showed that solar collectors can replace up to 19.6% of the thermal energy demand during the drying season. Bigger collectors and smaller air channels result in more useful heat, but attention has to be paid to costs and pressure drop, respectively. Annual monetary savings can reach up to THB 56,000 ({approx}US$ 1800 at US$ 1 THB 31). (author)

  14. VISA: a method for evaluating the performance of integrated safeguards systems at nuclear facilities

    International Nuclear Information System (INIS)

    Donnelly, H.; Fullwood, R.; Glancy, J.

    1977-06-01

    This is the second volume of a two volume report on the VISA method for evaluating safeguards at fixed-site facilities. This volume contains appendices that support the description of the VISA concept and the initial working version of the method, VISA-1, presented in Volume I. The information is separated into four appendices, each describing details of one of the four analysis modules that comprise the analysis sections of the method. The first appendix discusses Path Analysis methodology, applies it to a Model Fuel Facility, and describes the computer codes that are being used. Introductory material on Path Analysis given in Chapter 3.2.1 and Chapter 4.2.1 of Volume I. The second appendix deals with Detection Analysis, specifically the schemes used in VISA-1 for classifying adversaries and the methods proposed for evaluating individual detection mechanisms in order to build the data base required for detection analysis. Examples of evaluations on identity-access systems, SNM portal monitors, and intrusion devices are provided. The third appendix describes the Containment Analysis overt-segment path ranking, the Monte Carlo engagement model, the network simulation code, the delay mechanism data base, and the results of a sensitivity analysis. The last appendix presents general equations used in Interruption Analysis for combining covert-overt segments and compares them with equations given in Volume I, Chapter 3

  15. Evaluation of the seismic integrity of a plutonium-handling facility

    International Nuclear Information System (INIS)

    Coats, D.W.

    1981-01-01

    Many studies have been made by and for the Lawrence Livermore National Laboratory (LLNL) to ensure the seismic safety of its Plutonium Facility (Building 332). These studies have included seismological and geologic field investigations to define the actual seismic hazard existing at the Laboratory site as well as structural studies of the Facility itself. Because the basic seismic design criteria has undergone changes over the years, numerous structural studies and upgrades have been completed. The seismic criteria in use at the LLNL site is reviewed on a continuing basis as new information on the seismicity and geology of the Livermore Valley is obtained. At present, the Laboratory's Earth Sciences Division is conducting a multi-million dollar program to identify and characterize the geologic hazards at the Livermore site, with the primary emphasis on earthquake hazards in the Livermore Valley. This effort is undergoing an independent review by Woodward-Clyde Associates. Additionally, because of increased concerns over the seismic safety of Building 332, the Laboratory has initiated an independent structural review. This review effort will be monitored by the California Seismic Safety Commission to ensure its independence. Both of these studiies are in their early stages and results are not yet available

  16. The Multi-User Droplet Combustion Apparatus: the Development and Integration Concept for Droplet Combustion Payloads in the Fluids and Combustion Facility Combustion Integrated Rack

    Science.gov (United States)

    Myhre, C. A.

    2002-01-01

    The Multi-user Droplet Combustion Apparatus (MDCA) is a multi-user facility designed to accommodate four different droplet combustion science experiments. The MDCA will conduct experiments using the Combustion Integrated Rack (CIR) of the NASA Glenn Research Center's Fluids and Combustion Facility (FCF). The payload is planned for the International Space Station. The MDCA, in conjunction with the CIR, will allow for cost effective extended access to the microgravity environment, not possible on previous space flights. It is currently in the Engineering Model build phase with a planned flight launch with CIR in 2004. This paper provides an overview of the capabilities and development status of the MDCA. The MDCA contains the hardware and software required to conduct unique droplet combustion experiments in space. It consists of a Chamber Insert Assembly, an Avionics Package, and a multiple array of diagnostics. Its modular approach permits on-orbit changes for accommodating different fuels, fuel flow rates, soot sampling mechanisms, and varying droplet support and translation mechanisms to accommodate multiple investigations. Unique diagnostic measurement capabilities for each investigation are also provided. Additional hardware provided by the CIR facility includes the structural support, a combustion chamber, utilities for the avionics and diagnostic packages, and the fuel mixing capability for PI specific combustion chamber environments. Common diagnostics provided by the CIR will also be utilized by the MDCA. Single combustible fuel droplets of varying sizes, freely deployed or supported by a tether are planned for study using the MDCA. Such research supports how liquid-fuel-droplets ignite, spread, and extinguish under quiescent microgravity conditions. This understanding will help us develop more efficient energy production and propulsion systems on Earth and in space, deal better with combustion generated pollution, and address fire hazards associated with

  17. A DOE/DP multisite approach to safeguards integration with facility operations

    International Nuclear Information System (INIS)

    Ostenak, C.A.

    1987-01-01

    The Accountability Technology Exchange (ATEX) Working Group was established in October 1986 by the plutonium processing technology exchange steering committee under the US Department of Energy/Department of Defense program's materials management executive committee (DOE/DP MMEC). The ATEX Working Group provides a multisite, multidisciplinary forum for discussing, evaluating, and recommending both existing and emerging nuclear materials accountability measurement technologies for implementation into DOE/DP plutonium processing facilities. This forum assists technologists in understanding state-of-the-art plutonium processing and accountability measurement practices throughout the complex, as well as current and projected technical needs. As a result, the ATEX Working Group will contribute to the improvement of plutonium processing technologies by helping to assure that the best possible nuclear materials accountability measurement techniques are made available to all sites to process plutonium safely, securely, and cost-effectively

  18. Oregon state university's advanced plant experiment (APEX) AP1000 integral facility test program

    International Nuclear Information System (INIS)

    Reyes, J.N.; Groome, J.T.; Woods, B.G.; Young, E.; Abel, K.; Wu, Q.

    2005-01-01

    Oregon State University (OSU) has recently completed a three year study of the thermal hydraulic behavior of the Westinghouse AP1000 passive safety systems. Eleven Design Basis Accident (DBA) scenarios, sponsored by the U.S. Department of Energy (DOE) with technical support from Westinghouse Electric, were simulated in OSU's Advanced Plant Experiment (APEX)-1000. The OSU test program was conducted within the purview of the requirements of 10CFR50 Appendix B, NQA-1 and 10 CFR 21 and the test data was used to provide benchmarks for computer codes used in the final design approval of the AP1000. In addition to the DOE certification testing, OSU conducted eleven confirmatory tests for the U.S. Nuclear Regulatory Commission. This paper presents the test program objectives, a description of the APEX-1000 test facility and an overview of the test matrix that was conducted in support of plant certification. (authors)

  19. Integrative approach for wastewater treatment facilities with biomass transformation into energy

    OpenAIRE

    Anker Yaakov; Mualem David; Langstadter Hagai; Nakonechny Faina; Nisnevitch Marina

    2017-01-01

    Current industrial environmental regulations favor processes with Integrative Pollution Prevention and Control (IPPC). While several systems are regarded by different international directives as IPPC Best Available Techniques or Technologies (BAT), none of these systems are capable handling various pollutants of both gaseous and aquatic effluents. Additional hinder to a BAT-IPPC complete procedure are hazardous or uneconomical byproducts of the IPPC processes and significant auxiliary costs f...

  20. How an integrated change programme has accelerated the reduction in high hazard nuclear facilities at Sellafield

    International Nuclear Information System (INIS)

    Mackintosh, Angela

    2013-01-01

    For over five decades the Sellafield Site has been central to the UK's nuclear programme. Now operated by Sellafield Ltd, under the management of Parent Body Organisation Nuclear Management Partners (NMP), a consortium of URS Washington Division, AMEC and AREVA is focussed on the decommissioning of historical facilities. When Decommissioning commenced in the late 1980's the site focus at that time was on commercial reprocessing and waste management. Now through the implementation of a company change programme, emphasis has shifted towards accelerated risk and hazard reduction of degraded legacy plants with nuclear inventory whilst ensuring value for money for the customer, the Nuclear Decommissioning Authority. This paper will describe the management success by the Site owners in delivering a successful change programme. The paper will explain how the site has transitioned to the INPO Standard Nuclear Performance Model (SNPM) and how through the use of a change maturity matrix has contributed to the accelerated reduction in high risk high hazard nuclear facilities. The paper will explain in detail how the Decommissioning Programme Office has facilitated and coordinated the Governance and assured delivery of the change plan and how successful application of visual management has aided the communication of its progress. Finally, the paper will discuss how the Delivery Schedules have proved critical for presenting the change plan to Key Stakeholders, Government Owners and Powerful Regulators. Overall, this paper provides an insight into how a massive change programme is being managed within one of the world's highest regulated industries. (authors)

  1. How an integrated change programme has accelerated the reduction in high hazard nuclear facilities at Sellafield

    Energy Technology Data Exchange (ETDEWEB)

    Mackintosh, Angela [Change Manager, Decommissioning, Sellafield Ltd, Seascale, Cumbria (United Kingdom)

    2013-07-01

    For over five decades the Sellafield Site has been central to the UK's nuclear programme. Now operated by Sellafield Ltd, under the management of Parent Body Organisation Nuclear Management Partners (NMP), a consortium of URS Washington Division, AMEC and AREVA is focussed on the decommissioning of historical facilities. When Decommissioning commenced in the late 1980's the site focus at that time was on commercial reprocessing and waste management. Now through the implementation of a company change programme, emphasis has shifted towards accelerated risk and hazard reduction of degraded legacy plants with nuclear inventory whilst ensuring value for money for the customer, the Nuclear Decommissioning Authority. This paper will describe the management success by the Site owners in delivering a successful change programme. The paper will explain how the site has transitioned to the INPO Standard Nuclear Performance Model (SNPM) and how through the use of a change maturity matrix has contributed to the accelerated reduction in high risk high hazard nuclear facilities. The paper will explain in detail how the Decommissioning Programme Office has facilitated and coordinated the Governance and assured delivery of the change plan and how successful application of visual management has aided the communication of its progress. Finally, the paper will discuss how the Delivery Schedules have proved critical for presenting the change plan to Key Stakeholders, Government Owners and Powerful Regulators. Overall, this paper provides an insight into how a massive change programme is being managed within one of the world's highest regulated industries. (authors)

  2. Evidence-based practices to increase hand hygiene compliance in health care facilities: An integrated review.

    Science.gov (United States)

    Neo, Jun Rong Jeffrey; Sagha-Zadeh, Rana; Vielemeyer, Ole; Franklin, Ella

    2016-06-01

    Hand hygiene (HH) in health care facilities is a key component to reduce pathogen transmission and nosocomial infections. However, most HH interventions (HHI) have not been sustainable. This review aims to provide a comprehensive summary of recently published evidence-based HHI designed to improve HH compliance (HHC) that will enable health care providers to make informed choices when allocating limited resources to improve HHC and patient safety. The Medline electronic database (using PubMed) was used to identify relevant studies. English language articles that included hand hygiene interventions and related terms combined with health care environments or related terms were included. Seventy-three studies that met the inclusion criteria were summarized. Interventions were categorized as improving awareness with education, facility design, and planning, unit-level protocols and procedures, hospital-wide programs, and multimodal interventions. Past successful HHIs may not be as effective when applied to other health care environments. HH education should be interactive and engaging. Electronic monitoring and reminders should be implemented in phases to ensure cost-effectiveness. To create hospitalwide programs that engage end users, policy makers should draw expertise from interdisciplinary fields. Before implementing the various components of multimodal interventions, health care practitioners should identify and examine HH difficulties unique to their organizations. Future research should seek to achieve the following: replicate successful HHI in other health care environments, develop reliable HHC monitoring tools, understand caregiver-patient-family interactions, examine ways (eg, hospital leadership, financial support, and strategies from public health and infection prevention initiatives) to sustain HHC, and use simulated lab environments to refine study designs. Copyright © 2016 Association for Professionals in Infection Control and Epidemiology, Inc

  3. Integrated systems of monitoring and environmental data processing for nuclear facilities

    International Nuclear Information System (INIS)

    Diaconu, C.; Guta, V.; Oprea, I.; Oprea, M.; Stoica, M.; Pirvu, V.; Vasilache, E.; Pirvu, I.

    2001-01-01

    The processing of huge amount of data necessary to assess the real radiological situation both in normal operational conditions and during accidents requires an efficient system of monitoring and data processing. It must be able to secure information for the complex systems of radioactivity control aiming at evaluating the nuclear accident consequences and establishing a basis for correct decision making in the field of civil protection. The integrated environmental monitoring systems are based on a number of fixed and mobile installations, a meteorological parameter measurement station, a center for data processing and a communication network, working all under the control of a real-time operation system. They collect, and process the radioactivity level and meteorological data and transmit them through the communication network. The local monitoring stations are made of detector ensembles with pressurized ionization chambers and autonomous units providing continuously information on dose and integrated rates, average values as well as the current state of the station. The meteorological data acquisition station supplies information concerning wind direction and speed, the temperature and precipitation level. The information processing center is based on a PC integrated in a local network which collects data from the radiation monitoring equipment, meteorological station as well as other work stations which process various dosimetric parameters. It is connected to Internet, so ensuring fast transfer of information towards interested authorities. The communication network consists in a local or extended Ethernet network, radio or serial connections for radioactivity level monitoring units which can be stationary, portable or mobile. Requirements raised by the application of geographic information system (GIS) and the real time operation system (QNX) ensuring multiuser and multitask operations are discussed

  4. High Temperature Heat Pump Integration using Zeotropic Working Fluids for Spray Drying Facilities

    DEFF Research Database (Denmark)

    Zühlsdorf, Benjamin; Bühler, Fabian; Mancini, Roberta

    2017-01-01

    source and sink best possibly. Therefore, a set of six common working fluids is defined and the possible binary mixtures of these fluids are analyzed. The performance of the fluids is evaluated based on the energetic performance (COP) and the economic potential (NPV). The results show...... and show a large potential to reuse the excess heat from exhaust gases. This study analyses a heat pump application with an improved integration by choosing the working fluid as a mixture in such a way, that the temperature glide during evaporation and condensation matches the temperature glide of the heat...

  5. Facile integration of multiple magnetite nanoparticles for theranostics combining efficient MRI and thermal therapy

    Science.gov (United States)

    Huang, Guoming; Zhu, Xianglong; Li, Hui; Wang, Lirong; Chi, Xiaoqin; Chen, Jiahe; Wang, Xiaomin; Chen, Zhong; Gao, Jinhao

    2015-01-01

    Multifunctional nanostructures with both diagnostic and therapeutic capabilities have attracted considerable attention in biomedical research because they can offer great advantages in disease management and prognosis. In this work, a facile way to transfer the hydrophobic iron oxide (IO) nanoparticles into aqueous media by employing carboxylic graphene oxide (GO-COOH) as the transferring agent has been reported. In this one-step process, IO nanoparticles adhere to GO-COOH and form water-dispersible clusters via hydrophobic interactions between the hydrophobic ligands of IO nanoparticles and the basal plane of GO-COOH. The multiple IO nanoparticles on GO-COOH sheets (IO/GO-COOH) present a significant increase in T2 contrast enhancement. Moreover, the IO/GO-COOH nanoclusters also display a high photothermal conversion efficiency and can effectively inhibit tumor growth through the photothermal effects. It is envisioned that such IO/GO-COOH nanocomposites combining efficient MRI and photothermal therapy hold great promise in theranostic applications.Multifunctional nanostructures with both diagnostic and therapeutic capabilities have attracted considerable attention in biomedical research because they can offer great advantages in disease management and prognosis. In this work, a facile way to transfer the hydrophobic iron oxide (IO) nanoparticles into aqueous media by employing carboxylic graphene oxide (GO-COOH) as the transferring agent has been reported. In this one-step process, IO nanoparticles adhere to GO-COOH and form water-dispersible clusters via hydrophobic interactions between the hydrophobic ligands of IO nanoparticles and the basal plane of GO-COOH. The multiple IO nanoparticles on GO-COOH sheets (IO/GO-COOH) present a significant increase in T2 contrast enhancement. Moreover, the IO/GO-COOH nanoclusters also display a high photothermal conversion efficiency and can effectively inhibit tumor growth through the photothermal effects. It is envisioned

  6. Formulation of an Integrated Community Based Disaster Management for Hydroelectric facilities: The Malaysia Case

    Science.gov (United States)

    Hijazzi, Norshamirra; Thiruchelvam, Sivadass; Sabri Muda, Rahsidi; Nasharuddin Mustapha, Kamal; Che Muda, Zakaria; Ghazali, Azrul; Kamal Kadir, Ahmad; Hakimie, Hazlinda; Sahari, Khairul Salleh Mohamed; Hasini, Hasril; Mohd Sidek, Lariyah; Itam, Zarina; Fadhli Mohamad, Mohd; Razad, Azwin Zailti Abdul

    2016-03-01

    Dams, however significant their contributions are to the society, are not immune to failures and diminishing lifespan not unlike other structural elements in our infrastructure. Despite continuing efforts on design, construction, operation, and maintenance of dams to improve the safety of the dams, the possibility of unforeseen events of dam failures is still possible. Seeing that dams are usually integrated into close approximities with the community, dam failures may consequent in tremendous loss of lives and properties. The aims of formulation of Integrated Community Based Disaster Management (ICBDM) is to simulate evacuation modelling and emergency planning in order to minimize loss of life and property damages in the event of a dam-related disaster. To achieve the aim above, five main pillars have been identified for the formulation of ICBDM. A series of well-defined program inclusive of hydrological 2-D modelling, life safety modelling, community based EWS and CBTAP will be conducted. Finally, multiple parties’ engagement is to be carried out in the form of table top exercise to measure the readiness of emergency plans and response capabilities of key players during the state of a crisis.

  7. TiO2 nanowires for potential facile integration of solar cells and electrochromic devices

    International Nuclear Information System (INIS)

    Qiang, Pengfei; Chen, Zhongwei; Yang, Peihua; Liu, Pengyi; Mai, Wenjie; Cai, Xiang; Tan, Shaozao

    2013-01-01

    Self-powered systems usually consist of energy-acquisition components, energy-storage components and functional components. The development of nanoscience and nanotechnology has greatly improved the performance of all the components of self-powered systems. However, huge differences in the materials and configurations in the components cause large difficulties for integration and miniaturization of self-powered systems. Design and fabrication of different components in a self-powered system with the same or similar materials/configurations should be able to make the above goal easier. In this work, a proof-of-concept experiment involving an integrated self-powered color-changing system consisting of TiO 2 nanowire based sandwich dye-sensitized solar cells (DSSCs) and electrochromic devices (ECDs) is designed and demonstrated. When sunlight illuminates the entire system, the DSSCs generate electrical power and turn the ECD to a darker color, dimming the light; by switching the connection polarity of the DSSCs, the lighter color can be regained, implying the potential application of this self-powered color-changing system for next generation sun glasses and smart windows. (paper)

  8. Implementation and operational experience of an integrated fuel information service at the BNFL THORP facility

    International Nuclear Information System (INIS)

    Robson, D.N.; Ramsden, P.N.

    1995-01-01

    BNFL's THORP Plant, which started active operations early in 1994, has contracts to reprocess 7000t(U) of fuel belonging to 33 customers in 9 countries in the UK, Europe and Japan during its first 10 years of operation. Contracts are in place or being negotiated, and further business sought after, with the expectation of extending THORP's operations well beyond the initial 10 years. An integrated data management service, for the fuel storage areas of BNFL's THORP Division, is being implemented to replace several, independent, systems. This Fuel Information Service (FIS) will bring the Nuclear Materials Accountancy and Safeguards Records together with the Operating Records into one database from which all Safeguards Reports will be made. BNFL's contractual and commercial data and technical data on the stored fuel, required to support the reprocessing business, will also be brought into the common database. FIS is the first stage in a project to integrate the Materials Management systems throughout the THORP nuclear recycling business including irradiated fuel receipt and storage, reprocessing and storage of products, mixed oxide fuel manufacture and the conditioning and storage of wastes

  9. Integrative Review of Facility Interventions to Manage Compassion Fatigue in Oncology Nurses.

    Science.gov (United States)

    Wentzel, Dorien; Brysiewicz, Petra

    2017-05-01

    Oncology nurses are regularly exposed to high-stress situations that may lead to compassion fatigue, and many institutions have implemented interventions to reduce burnout in nurses, but knowledge on the feasiblity, effectiveness, and nurses' experience of interventions is lacking.
. Electronic search of literature published from 1992-2015 was performed to evaluate in-facility interventions to manage compassion fatigue in oncology nurses. Databases used included CINAHL®, PubMed, Web of Science, Google Scholar, and PsycINFO®. 
. The goal was to evaluate the effectiveness, feasibility, and nurses' experience of interventions to manage compassion fatigue. The study designs, methods, and limitations were independently screened by the authors. 
. Of 164 studies, 31 met eligibility criteria. 
. The majority of the studies were conducted in Western countries, which suggests the need for additional research in other settings to determine effective interventions that address compassion fatigue and stress cross-culturally. Quantitative and qualitative studies failed to gain high scores in terms of quality. Limited conclusions can be drawn from small studies that report on outcomes with many confounding variables, such as turnover rate or general health of nurses, from a single institution. 
. Lack of empirical precision in evaluating the effectiveness, feasibility, and nurses' experiences of interventions indicates a need for future, more rigorously designed experimental studies. Because of the global increase in the number of patients being diagnosed and living with cancer, oncology nurses should be able to recognize and manage compassion fatigue.

  10. System integration of RF based negative ion experimental facility at IPR

    Science.gov (United States)

    Bansal, G.; Bandyopadhyay, M.; Singh, M. J.; Gahlaut, A.; Soni, J.; Pandya, K.; Parmar, K. G.; Sonara, J.; Chakraborty, A.

    2010-02-01

    The setting up of RF based negative ion experimental facility shall witness the beginning of experiments on the negative ion source fusion applications in India. A 1 MHz RF generator shall launch 100 kW RF power into a single driver on the plasma source to produce a plasma of density ~5 × 1012 cm-3. The source can deliver a negative ion beam of ~10 A with a current density of ~30 mA/cm2 and accelerated to 35 kV through an electrostatic ion accelerator. The experimental system is similar to a RF based negative ion source, BATMAN, presently operating at IPP. The subsystems for source operation are designed and procured principally from indigenous resources, keeping the IPP configuration as a base line. The operation of negative ion source is supported by many subsystems e.g. vacuum pumping system with gate valves, cooling water system, gas feed system, cesium delivery system, RF generator, high voltage power supplies, data acquisition and control system, and different diagnostics. The first experiments of negative ion source are expected to start at IPR from the middle of 2009.

  11. System integration of RF based negative ion experimental facility at IPR

    International Nuclear Information System (INIS)

    Bansal, G; Bandyopadhyay, M; Singh, M J; Gahlaut, A; Soni, J; Pandya, K; Parmar, K G; Sonara, J; Chakraborty, A

    2010-01-01

    The setting up of RF based negative ion experimental facility shall witness the beginning of experiments on the negative ion source fusion applications in India. A 1 MHz RF generator shall launch 100 kW RF power into a single driver on the plasma source to produce a plasma of density ∼5 x 10 12 cm -3 . The source can deliver a negative ion beam of ∼10 A with a current density of ∼30 mA/cm 2 and accelerated to 35 kV through an electrostatic ion accelerator. The experimental system is similar to a RF based negative ion source, BATMAN, presently operating at IPP. The subsystems for source operation are designed and procured principally from indigenous resources, keeping the IPP configuration as a base line. The operation of negative ion source is supported by many subsystems e.g. vacuum pumping system with gate valves, cooling water system, gas feed system, cesium delivery system, RF generator, high voltage power supplies, data acquisition and control system, and different diagnostics. The first experiments of negative ion source are expected to start at IPR from the middle of 2009.

  12. The structural biology center at the APS: an integrated user facility for macromolecular crystallography

    International Nuclear Information System (INIS)

    Rosenbaum, G.; Westbrook, E.M.

    1997-01-01

    The Structural Biology Center (SBC) has developed and operates a sector (undulator and bending magnet) of the APS as a user facility for macromolecular crystallography. Crystallographically determined structures of proteins, nucleic acids and their complexes with proteins, viruses, and complexes between macromolecules and small ligands have become of central importance in molecular and cellular biology. Major design goals were to make the extremely high brilliance of the APS available for brilliance limited studies, and to achieve a high throughput of less demanding studies, as well as optimization for MAS-phasing. Crystal samples will include extremely small crystals, crystals with large unit cells (viruses, ribosomes, etc.) and ensembles of closely similar crystal structures for drug design, protein engineering, etc. Data are recorded on a 3000x3000 pixel CCD-area detector (optionally on image plates). The x-ray optics of both beamlines has been designed to produce a highly demagnified image of the source in order to match the focal size with the sizes of the sample and the resolution element of the detector. Vertical focusing is achieved by a flat, cylindrically bent mirror. Horizontal focusing is achieved by sagitally bending the second crystal of the double crystal monochromator. Monochromatic fluxes of 1.3 * 10 13 ph/s into focal sizes of 0.08 mm (horizontal)x0.04 mm (vertical) FWHM (flux density 3.5 * 10 15 ph/s/mm 2 ) have been recorded.copyright 1997 American Institute of Physics

  13. Investigation of accident management procedures related to loss of feedwater and station blackout in PSB-VVER integral test facility

    Energy Technology Data Exchange (ETDEWEB)

    Bucalossi, A. [EC JRC, (JRC F.5) PO Box 2, 1755 ZG Petten (Netherlands); Del Nevo, A., E-mail: alessandro.delnevo@enea.it [ENEA, C.R. Brasimone, 40032 Camugnano (Italy); Moretti, F.; D' Auria, F. [GRNSPG, Universita di Pisa, via Diotisalvi 2, 56100 Pisa (Italy); Elkin, I.V.; Melikhov, O.I. [Electrogorsk Research and Engineering Centre, Electrogorsk, Moscow Region (Russian Federation)

    2012-09-15

    Highlights: Black-Right-Pointing-Pointer Four integral test facility experiments related to VVER-1000 reactor. Black-Right-Pointing-Pointer TH response of the VVER-1000 primary system following total loss of feedwater and station blackout scenarios. Black-Right-Pointing-Pointer Accident management procedures in case of total loss of feedwater and station blackout. Black-Right-Pointing-Pointer Experimental data represent an improvement of existing database for TH code validation. - Abstract: VVER 1000 reactors have some unique and specific features (e.g. large primary and secondary side fluid inventory, horizontal steam generators, core design) that require dedicated experimental and analytical analyses in order to assess the performance of safety systems and the effectiveness of possible accident management strategies. The European Commission funded project 'TACIS 2.03/97', Part A, provided valuable experimental data from the large-scale (1:300) PSB-VVER test facility, investigating accident management procedures in VVER-1000 reactor. A test matrix was developed at University of Pisa (responsible of the project) with the objective of obtaining the experimental data not covered by the OECD VVER validation matrix and with main focus on accident management procedures. Scenarios related to total loss of feed water and station blackout are investigated by means of four experiments accounting for different countermeasures, based on secondary cooling strategies and primary feed and bleed procedures. The transients are analyzed thoroughly focusing on the identification of phenomena that will challenge the code models during the simulations.

  14. Development of stress corrosion techniques for structural integrity evaluation and life extension of PWR facilities

    International Nuclear Information System (INIS)

    Moreira, Pedro A.L.D.L. Pinheiro; Vilela, Jeferson J.; Lorenzo, Roberto F. Di; Lopes, Jadir A.M.

    2000-01-01

    The stress corrosion is a mechanism of degradation present in the nuclear plants. To extend the life of the plants components, this corrosion type it should be known. An evaluation for the implantation of methodologies of stress corrosion study in CDTN/CNEN, shows that the technique of slow deformation can be used in the evaluation of integrity structural nuclear power stations. This technique consists of straining a sample slowly, usually, in strain rate between 10 -4 and 10- 8 s -1 and in conditions that simulate the reactivity of the metal in environment (pressure, temperature, chemical composition of the water and etc) similar to the found at the nuclear power power stations. This simulation allows evaluating susceptibility the stress corrosion of components mechanical and structure that operate in central nuclear. (author)

  15. Fuel cycle facility control system for the Integral Fast Reactor Program

    International Nuclear Information System (INIS)

    Benedict, R.W.; Tate, D.A.

    1993-01-01

    As part of the Integral Fast Reactor (IFR) Fuel Demonstration, a new distributed control system designed, implemented and installed. The Fuel processes are a combination of chemical and machining processes operated remotely. To meet this special requirement, the new control system provides complete sequential logic control motion and positioning control and continuous PID loop control. Also, a centralized computer system provides near-real time nuclear material tracking, product quality control data archiving and a centralized reporting function. The control system was configured to use programmable logic controllers, small logic controllers, personal computers with touch screens, engineering work stations and interconnecting networks. By following a structured software development method the operator interface was standardized. The system has been installed and is presently being tested for operations

  16. Implementation of the Integrated Alarm System for KOMAC facility using EPICS framework and Eclipse

    International Nuclear Information System (INIS)

    Song, Young-Gi; Kim, Jae-Ha; Kim, Han-Sung; Kwon, Hyeok-Jung; Cho, Yong-Sub

    2017-01-01

    The alarm detecting layer is the component that monitors alarm signals which are transported to the processing part through message queue. The main purpose of the processing part is to transfer the alarm signals connecting an alarm identification and state of the alarm to database system. The operation interface of system level signal links has been developed by EPICS framework. EPICS tools have been used for monitoring device alarm status. The KOMAC alarm system was developed for offering a user-friendly, intuitive user interface. The alarm system is implemented with EPICS IOC for alarm server, eclipse-mars integrated development tool for alarm viewer, and mariadb for alarm log. The new alarm system supports intuitive user interface on alarm information and alarm history. Alarm view has plans to add login function, user permission on alarm acknowledge, user permission of PV import, search and report function.

  17. Economic and Environmental Evaluation of Flexible Integrated Gasification Polygeneration Facilities Equipped with Carbon Capture and Storage

    Science.gov (United States)

    Aitken, M.; Yelverton, W. H.; Dodder, R. S.; Loughlin, D. H.

    2014-12-01

    Among the diverse menu of technologies for reducing greenhouse gas (GHG) emissions, one option involves pairing carbon capture and storage (CCS) with the generation of synthetic fuels and electricity from co-processed coal and biomass. In this scheme, the feedstocks are first converted to syngas, from which a Fischer-Tropsch (FT) process reactor and combined cycle turbine produce liquid fuels and electricity, respectively. With low concentrations of sulfur and other contaminants, the synthetic fuels are expected to be cleaner than conventional crude oil products. And with CO2 as an inherent byproduct of the FT process, most of the GHG emissions can be eliminated by simply compressing the CO2 output stream for pipeline transport. In fact, the incorporation of CCS at such facilities can result in very low—or perhaps even negative—net GHG emissions, depending on the fraction of biomass as input and its CO2 signature. To examine the potential market penetration and environmental impact of coal and biomass to liquids and electricity (CBtLE), which encompasses various possible combinations of input and output parameters within the overall energy landscape, a system-wide analysis is performed using the MARKet ALlocation (MARKAL) model. With resource supplies, energy conversion technologies, end-use demands, costs, and pollutant emissions as user-defined inputs, MARKAL calculates—using linear programming techniques—the least-cost set of technologies that satisfy the specified demands subject to environmental and policy constraints. In this framework, the U.S. Environmental Protection Agency (EPA) has developed both national and regional databases to characterize assorted technologies in the industrial, commercial, residential, transportation, and generation sectors of the U.S. energy system. Here, the EPA MARKAL database is updated to include the costs and emission characteristics of CBtLE using figures from the literature. Nested sensitivity analysis is then

  18. Technoeconomic analysis of an integrated microalgae photobioreactor, biodiesel and biogas production facility

    International Nuclear Information System (INIS)

    Harun, Razif; Davidson, Michael; Doyle, Mark; Gopiraj, Rajprathab; Danquah, Michael; Forde, Gareth

    2011-01-01

    As fossil fuel prices increase and environmental concerns gain prominence, the development of alternative fuels from biomass has become more important. Biodiesel produced from microalgae is becoming an attractive alternative to share the role of petroleum. Currently it appears that the production of microalgal biodiesel is not economically viable in current environment because it costs more than conventional fuels. Therefore, a new concept is introduced in this article as an option to reduce the total production cost of microalgal biodiesel. The integration of biodiesel production system with methane production via anaerobic digestion is proved in improving the economics and sustainability of overall biodiesel stages. Anaerobic digestion of microalgae produces methane and further be converted to generate electricity. The generated electricity can surrogate the consumption of energy that require in microalgal cultivation, dewatering, extraction and transesterification process. From theoretical calculations, the electricity generated from methane is able to power all of the biodiesel production stages and will substantially reduce the cost of biodiesel production (33% reduction). The carbon emissions of biodiesel production systems are also reduced by approximately 75% when utilizing biogas electricity compared to when the electricity is otherwise purchased from the Victorian grid. The overall findings from this study indicate that the approach of digesting microalgal waste to produce biogas will make the production of biodiesel from algae more viable by reducing the overall cost of production per unit of biodiesel and hence enable biodiesel to be more competitive with existing fuels. (author)

  19. Design concepts for an integrated control room used as a site-wide operations facility

    International Nuclear Information System (INIS)

    Simon, B.H.; Raghavan, R.; Ujita, H.; Utena, S.; Sakuma, A.; Itoh, T.; Fukura, M.; Ono, I.

    1995-01-01

    The concept of an Integrated Main Control Room (IMCR) evolved from surveys conducted by Tokyo Electric Power Company (TEPCO) with plant managers and workers as their existing GE-type boiling water reactors (BWRs) on the need for improved operating conditions in a new generation of reactors being developed for the next century (around 2010). These reactors will be a further enhancement of the advanced boiling water reactors (ABWRs) now being constructed at the Kashiwazaki-Kariwa site in Japan (no.6 and no.7). TEPCO also saw a need for new thinking on control room design because of projected social conditions in Japan for the 21st century. These projections forecast a smaller number of skilled engineering graduates and those graduates less willing to work in nuclear power because such work is seen as unappealing, conducted in remote geographical locations, and requiring extensive night duty. As one solution to reducing operator burden and decreasing the night shift staff, while making nuclear plant operation more interesting for the operators and reducing labor and construction costs, the IMCR was conceived. (author)

  20. Integrated ground-water monitoring strategy for NRC-licensed facilities and sites: Case study applications

    Science.gov (United States)

    Price, V.; Temples, T.; Hodges, R.; Dai, Z.; Watkins, D.; Imrich, J.

    2007-01-01

    This document discusses results of applying the Integrated Ground-Water Monitoring Strategy (the Strategy) to actual waste sites using existing field characterization and monitoring data. The Strategy is a systematic approach to dealing with complex sites. Application of such a systematic approach will reduce uncertainty associated with site analysis, and therefore uncertainty associated with management decisions about a site. The Strategy can be used to guide the development of a ground-water monitoring program or to review an existing one. The sites selected for study fall within a wide range of geologic and climatic settings, waste compositions, and site design characteristics and represent realistic cases that might be encountered by the NRC. No one case study illustrates a comprehensive application of the Strategy using all available site data. Rather, within each case study we focus on certain aspects of the Strategy, to illustrate concepts that can be applied generically to all sites. The test sites selected include:Charleston, South Carolina, Naval Weapons Station,Brookhaven National Laboratory on Long Island, New York,The USGS Amargosa Desert Research Site in Nevada,Rocky Flats in Colorado,C-Area at the Savannah River Site in South Carolina, andThe Hanford 300 Area.A Data Analysis section provides examples of detailed data analysis of monitoring data.

  1. Study of developing nuclear fabrication facility's integrated emergency response manual

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Taeh Yeong; Cho, Nam Chan; Han, Seung Hoon; Moon, Jong Han; Lee, Jin Hang [KEPCO, Daejeon (Korea, Republic of); Min, Guem Young; Han, Ji Ah [Dongguk Univ., Daejeon (Korea, Republic of)

    2016-05-15

    Public begin to pay attention to emergency management. Thus, public's consensus on having high level of emergency management system up to advanced country's is reached. In this social atmosphere, manual is considered as key factor to prevent accident or secure business continuity. Therefore, we first define possible crisis at KEPCO Nuclear Fuel (hereinafter KNF) and also make a 'Reaction List' for each crisis situation at the view of information-design. To achieve it, we analyze several country's crisis response manual and then derive component, indicate duties and roles at the information-design point of view. From this, we suggested guideline to make 'Integrated emergency response manual(IERM)'. The manual we used before have following few problems; difficult to applicate at the site, difficult to deliver information. To complement these problems, we searched manual elements from the view of information-design. As a result, we develop administrative manual. Although, this manual could be thought as fragmentary manual because it confined specific several agency/organization and disaster type.

  2. Design and fabrication of a 50 MWt prototypical MHD coal-fired combustor

    International Nuclear Information System (INIS)

    Albright, J.; Braswell, R.; Listvinsky, G.; McAllister, M.; Myrick, S.; Ono, D.; Thom, H.

    1992-01-01

    A prototypical 50 MWt coal-fired combustor has been designed and fabricated as part of the Magnetohydrodynamic (MHD) Integrated Topping Cycle (ITC) Program. This is a DOE-funded program to develop a prototypical MHD power train to be tested at the Component Development and Integration Facility (CDIF) in Butte, Montana. The prototypical combustor is an outgrowth of the 50 MWt workhorse combustor which has previously been tested at the CDIF. In addition to meeting established performance criteria of the existing 50 MWt workhorse combustor, the prototypical combustor design is required to be scaleable for use at the 250 MWt retrofit level. This paper presents an overview of the mechanical design of the prototypical combustor and a description of its fabrication. Fabrication of the 50 MWt prototypical coal-fired combustor was completed in February 1992 and hot-fire testing is scheduled to begin in May 1992

  3. Integration of a functionally graded W/Cu transition for divertor components of fusion facilities

    International Nuclear Information System (INIS)

    Pintsuk, G.

    2004-01-01

    /Cu-interlayer, OFHC-Cu (Oxygen free high conductivity) and CuCrZr will be done by hot isostatic pressing. Parameters are a temperature of 550 C an a pressure of 195 MPa. Electrochemical deposited copper and nickel are added. Copper is used as surface layer of the graded W/Cu-composite and nickel for the strengthening of the diffusion bonding. Ultra-sonic-testing revealed narrow areas with inhomogeneous bonding at the interface, mainly nearby the outer surface of the module. The module containing the macro-brush has been tested at the electron-beam test facility JUDITH. It survived power loads at steady state operation of 23.8 MW/m 2 and 150 cycles at 20 MW/m 2 during thermal fatigue experiments. These results verify, that the insertion of a graded W/Cu-interlayer increases the resistance against thermal loads. Especially in the combination with the castellated structure. (orig.)

  4. The MIT Integrated Global System Model: A facility for Assessing and Communicating Climate Change Uncertainty (Invited)

    Science.gov (United States)

    Prinn, R. G.

    2013-12-01

    The world is facing major challenges that create tensions between human development and environmental sustenance. In facing these challenges, computer models are invaluable tools for addressing the need for probabilistic approaches to forecasting. To illustrate this, I use the MIT Integrated Global System Model framework (IGSM; http://globalchange.mit.edu ). The IGSM consists of a set of coupled sub-models of global economic and technological development and resultant emissions, and physical, dynamical and chemical processes in the atmosphere, land, ocean and ecosystems (natural and managed). Some of the sub-models have both complex and simplified versions available, with the choice of which version to use being guided by the questions being addressed. Some sub-models (e.g.urban air pollution) are reduced forms of complex ones created by probabilistic collocation with polynomial chaos bases. Given the significant uncertainties in the model components, it is highly desirable that forecasts be probabilistic. We achieve this by running 400-member ensembles (Latin hypercube sampling) with different choices for key uncertain variables and processes within the human and natural system model components (pdfs of inputs estimated by model-observation comparisons, literature surveys, or expert elicitation). The IGSM has recently been used for probabilistic forecasts of climate, each using 400-member ensembles: one ensemble assumes no explicit climate mitigation policy and others assume increasingly stringent policies involving stabilization of greenhouse gases at various levels. These forecasts indicate clearly that the greatest effect of these policies is to lower the probability of extreme changes. The value of such probability analyses for policy decision-making lies in their ability to compare relative (not just absolute) risks of various policies, which are less affected by the earth system model uncertainties. Given the uncertainties in forecasts, it is also clear that

  5. Determinants of facility readiness for integration of family planning with HIV testing and counseling services: evidence from the Tanzania service provision assessment survey, 2014-2015.

    Science.gov (United States)

    Bintabara, Deogratius; Nakamura, Keiko; Seino, Kaoruko

    2017-12-22

    Global policy reports, national frameworks, and programmatic tools and guidance emphasize the integration of family planning and HIV testing and counseling services to ensure universal access to reproductive health care and HIV prevention. However, the status of integration between these two services in Tanzanian health facilities is unclear. This study examined determinants of facility readiness for integration of family planning with HIV testing and counseling services in Tanzania. Data from the 2014-2015 Tanzania Service Provision Assessment Survey were analyzed. Facilities were considered ready for integration of family planning with HIV testing and counseling services if they scored ≥ 50% on both family planning and HIV testing and counseling service readiness indices as identified by the World Health Organization. All analyses were adjusted for clustering effects, and estimates were weighted to correct for non-responses and disproportionate sampling. Descriptive, bivariate, and multivariate logistic regression analyses were performed. A total of 1188 health facilities were included in the study. Of all of the health facilities, 915 (77%) reported offering both family planning and HIV testing and counseling services, while only 536 (45%) were considered ready to integrate these two services. Significant determinants of facility readiness for integrating these two services were being government owned [AOR = 3.2; 95%CI, 1.9-5.6], having routine management meetings [AOR = 1.9; 95%CI, 1.1-3.3], availability of guidelines [AOR = 3.8; 95%CI, 2.4-5.8], in-service training of staff [AOR = 2.6; 95%CI, 1.3-5.2], and availability of laboratories for HIV testing [AOR = 17.1; 95%CI, 8.2-35.6]. The proportion of facility readiness for the integration of family planning with HIV testing and counseling in Tanzania is unsatisfactory. The Ministry of Health should distribute and ensure constant availability of guidelines, availability of rapid diagnostic

  6. Roll-to-Roll Inkjet Printing and Photonic Sintering of Electrodes for ITO Free Polymer Solar Cell Modules and Facile Product Integration

    DEFF Research Database (Denmark)

    Angmo, Dechan; Larsen-Olsen, Thue Trofod; Jørgensen, Mikkel

    2013-01-01

    Small polymer solar cell modules that are manufactured without indium-tin-oxide using only roll-to-roll printing and coating techniques under ambient conditions enable facile integration into a simple demonstrator (for example a laser pointer). Semitransparent front electrode grid structures prep...

  7. Validation of RETRAN-03 by simulating a peach bottom turbine trip and boiloff at the full integral simulation test facility

    International Nuclear Information System (INIS)

    Westacott, J.L.; Peterson, C.E.

    1992-01-01

    This paper reports that the RETRAN-03 computer code is validated by simulating two tests that were performed at the Full Integral Simulation Test (FIST) facility. The RETRAN-03 results of a turbine trip (test 4PTT1) and failure to maintain water level at decay power (test T1QUV) are compared with the FIST test data. The RETRAN-03 analysis of test 4PTT1 is compared with a previous TRAC-BWR analysis of the test. Sensitivity to various model nodalizations and RETRAN-03 slip options are studied by comparing results of test T1QUV. The predicted thermal-hydraulic responses of both tests agree well with the test data. The pressure response of test 4PTT1 and the boiloff rate for test T1QUV are accurately predicted. Core uncovery time is found to be sensitive to the upper downcomer and upper plenum nodalization. The RETRAN-03 algebraic and dynamic slip options produce similar results for test T1QUV

  8. An application of oscillation-damped motion for suspended payloads to the advanced integrated maintenance system in fuel cycle facilities

    International Nuclear Information System (INIS)

    Noakes, M.W.; Petterson, B.J.; Werner, J.C.

    1990-01-01

    The transportation of objects using overhead cranes can induce pendular motion of the object, which usually must be damped or allowed to decay before the next process can take place. Recent work at Sandia National Laboratories has shown that oscillation-damped transport and swing-free stops are possible by properly programming the acceleration of the transporting crane. Initial studies have been completed using a CIMCORP XR6100 gantry robot. The Advanced Integrated Maintenance System (AIMS) is an engineering and operations test bed developed for remote maintenance and handling studies within the Consolidated Fuel Reprocessing Program (CFRP) at Oak Ridge National Laboratory. The goal of CFRP has been to advanced the technology of in-cell systems planned for future nuclear fuel cycle facilities. The AIMS provides the capabilities to examine the needs and constraints necessary for hot-cell remote maintenance and includes a force-reflecting master/slave teleoperator and overhead transporter system. The associated control system provides a flexible programming environment conducive to controls experimentation. This paper reviews the theory associated with oscillation-damped trajectories for simply suspended objects and describes a specific implementation of the oscillation damping methods for the AIMS transporter. Hardware and software requirements and constraints for proper operation are discussed

  9. Assessment of the integrity of structural shielding of four computed tomography facilities in the greater Accra region of Ghana

    International Nuclear Information System (INIS)

    Nkansah, A.; Schandorf, C.; Boadu, M.; Fletcher, J. J.

    2013-01-01

    The structural shielding thicknesses of the walls of four computed tomography (CT) facilities in Ghana were re-evaluated to verify the shielding integrity using the new shielding design methods recommended by the National Council on Radiological Protection and Measurements (NCRP). The shielding thickness obtained ranged from 120 to 155 mm using default DLP values proposed by the European Commission and 110 to 168 mm using derived DLP values from the four CT manufacturers. These values are within the accepted standard concrete wall thickness ranging from 102 to 152 mm prescribed by the NCRP. The ultrasonic pulse testing of all walls indicated that these are of good quality and free of voids since pulse velocities estimated were within the range of 3.496±0.005 km s -1 . An average dose equivalent rate estimated for supervised areas is 3.4±0.27 μSv week -1 and that for the controlled area is 18.0±0.15 μSv week -1 , which are within acceptable values. (authors)

  10. Assessment of the structural shielding integrity of some selected computed tomography facilities in the Greater Accra Region of Ghana

    International Nuclear Information System (INIS)

    Nkansah, A.

    2010-01-01

    The structural shielding integrity was assessed for four of the CT facilities at Trust Hospital, Korle-Bu Teaching Hospital, the 37 Military Hospital and Medical Imaging Ghana Ltd. in the Greater Accra Region of Ghana. From the shielding calculations, the concrete wall thickness computed are 120, 145, 140 and 155mm, for Medical Imaging Ghana Ltd. 37 Military, Trust Hospital and Korle-Bu Teaching Hospital respectively using Default DLP values. The wall thickness using Derived DLP values are 110, 110, 120 and 168mm for Medical Imaging Ghana Ltd, 37 Military Hospital, Trust Hospital and Korle-Bu Teaching Hospital respectively. These values are within the accepted standard concrete thickness of 102- 152mm prescribed by the National Council of Radiological Protection and measurement. The ultrasonic pulse testing indicated that all the sandcrete walls are of good quality and free of voids since pulse velocities estimated were approximately equal to 3.45km/s. an average dose rate measurement for supervised areas is 3.4 μSv/wk and controlled areas is 18.0 μSv/wk. These dose rates were below the acceptable levels of 100 μSv per week for the occupationally exposed and 20 μSv per week for members of the public provided by the ICRU. The results mean that the structural shielding thickness are adequate to protect members of the public and occupationally exposed workers (au).

  11. An integrated approach to risk-based remediation of a former bulk fuel storage facility adjacent a marine environment

    Energy Technology Data Exchange (ETDEWEB)

    Kemp, L.; Hers, I. [Golder Associates Ltd., Vancouver, BC (Canada)

    2006-07-01

    An integrated approach to risk-based remediation of a former bulk fuel storage facility adjacent to a marine environment was discussed. The presentation provided an introduction and illustration to the site location and history, located close to Skagway, Alaska and northwestern British Columbia. The site investigation and conceptual model were also presented. The remedial approach was also described with reference to a risk-based action approach, remedial objectives, soil vapour extraction (SVE)-bioventing, and air sparging-biosparging. The objectives were to minimize potential exposure to aquatic receptors by minimizing non-aqueous phase liquids (NAPL) mobility and dissolved transport of petroleum hydrocarbons. Groundwater modeling to assess the attenuation rate and to determine remedial targets was also discussed. Model validation and results of groundwater modeling as well as remediation system details and performance were then provided. It was determined that significant attenuation is occurring and that effective mass removal and concentrations have been decreasing over time. It was demonstrated that risk-based remedial goals and hydrogeology can change with land use/development. tabs., figs.

  12. A web-based three-tier control and monitoring application for integrated facility management of photovoltaic systems

    Directory of Open Access Journals (Sweden)

    Apostolos Meliones

    2014-01-01

    Full Text Available The architecture of a control system can be designed vertically with the distinction between functional levels. We adopt this layered approach for the design and implementation of a network-based control and monitoring application. In this paper we present the design and implementation of a network-based management application for controlling and monitoring the input and output data of remote equipment aiming at performance macro-observation, alarm detection, handling operation failures, installation security, access control, collection and recording of statistical data and provisioning of reports. The main services provided to the user and operating over the public internet and/or mobile network include control, monitoring, notification, reporting and data export. Our proposed system consists of a front-end for field (site-level control and monitoring as well as a service back-end which undertakes to collect, store and manage data from all remote installations. Hierarchical data acquisition methodology and performance macro-observation are according to the IEC 61724 standard. We have successfully used our control and monitoring application for integrated facility management of photovoltaic plant installations; nevertheless it can be easily migrated to other renewable energy generation installations and remote automation applications in general.

  13. Use of Persistent Identifiers to link Heterogeneous Data Systems in the Integrated Earth Data Applications (IEDA) Facility

    Science.gov (United States)

    Hsu, L.; Lehnert, K. A.; Carbotte, S. M.; Arko, R. A.; Ferrini, V.; O'hara, S. H.; Walker, J. D.

    2012-12-01

    The Integrated Earth Data Applications (IEDA) facility maintains multiple data systems with a wide range of solid earth data types from the marine, terrestrial, and polar environments. Examples of the different data types include syntheses of ultra-high resolution seafloor bathymetry collected on large collaborative cruises and analytical geochemistry measurements collected by single investigators in small, unique projects. These different data types have historically been channeled into separate, discipline-specific databases with search and retrieval tailored for the specific data type. However, a current major goal is to integrate data from different systems to allow interdisciplinary data discovery and scientific analysis. To increase discovery and access across these heterogeneous systems, IEDA employs several unique IDs, including sample IDs (International Geo Sample Number, IGSN), person IDs (GeoPass ID), funding award IDs (NSF Award Number), cruise IDs (from the Marine Geoscience Data System Expedition Metadata Catalog), dataset IDs (DOIs), and publication IDs (DOIs). These IDs allow linking of a sample registry (System for Earth SAmple Registration), data libraries and repositories (e.g. Geochemical Research Library, Marine Geoscience Data System), integrated synthesis databases (e.g. EarthChem Portal, PetDB), and investigator services (IEDA Data Compliance Tool). The linked systems allow efficient discovery of related data across different levels of granularity. In addition, IEDA data systems maintain links with several external data systems, including digital journal publishers. Links have been established between the EarthChem Portal and ScienceDirect through publication DOIs, returning sample-level objects and geochemical analyses for a particular publication. Linking IEDA-hosted data to digital publications with IGSNs at the sample level and with IEDA-allocated dataset DOIs are under development. As an example, an individual investigator could sign up

  14. How an integrated change programme has accelerated the reduction in high hazard nuclear facilities at Sellafield - 59014

    International Nuclear Information System (INIS)

    Mackintosh, Angela

    2012-01-01

    For over five decades the Sellafield Site has been central to the UK's nuclear programme. Sellafield Ltd is managed by NMP (Nuclear Management Partners), a consortium of URS, AMEC and AREVA and is focussed on the decommissioning of historical facilities. When the activity of Decommissioning commenced in the late 1980's the site focus at that time was on commercial reprocessing and waste management. Now through the implementation of an integrated company change programme, emphasis has shifted towards accelerated risk and hazard reduction of degraded legacy plants with nuclear inventory whilst ensuring value for money for the customer, the Nuclear Decommissioning Authority (NDA). This paper will describe the management approach that is being taken and the planning tools that are being applied by the Site owners in delivering an integrated change programme across the Decommissioning Directorate. The paper will explain how the management approach to change uses Peer Assist, Rapid Improvement Events, Organisational Review Self Evaluation, Value Stream Analysis and Accelerated Improvement Events as improvement tools. Use of these has enabled down-sizing of the organisation, driven out hundreds of man day efficiencies within the maintenance and asset management areas, improved the management of spares reducing annual costs by Pounds 1000's, improved Commercial practices by fast tracking the preparation of invitations to tender for critical contracts, rolled back radiological control areas and enabled quicker access to the work-face at a reduced cost. This paper will explain in detail how the Decommissioning Directorate Programme Office has implemented planning tools such as governance, identification of opportunities, benefit evaluation and prioritisation and sanction of the optimum improvements and how through the use of a balanced scorecard, delivery of the improvements has been measured ensuring that the targets are met. Finally, the paper will discuss how the

  15. Integrated Test Bed Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The ITB's avionics system is composed of multiple high performance processors, embedded software, and data communication systems. The avionics embedded software is a...

  16. Integration of refrigerators into facility automation with the aid of bus systems; Integration der Kaeltetechnik in die Gebaeudeautomation mit Bus-Systemen

    Energy Technology Data Exchange (ETDEWEB)

    Baumgarth, S.; Heiser, M. [Fachhochschule Braunschweig-Wolfenbuettel, Wolfenbuettel (DE). Inst. fuer Verbrennungstechnik und Prozessautomation (IVP)

    2000-07-01

    The integration of refrigeration systems in building automation is illustrated by the example of a ventilation system and a cooling ceiling. Cold is supplied by a coldwater unit. This necessitates supply of consumption data to the central refrigeration system. So far, technical facilities are commonly controlled by DDC systems and in-house bus systems. The demand for open communication between different systems resulted in the development of neutral systems like FND and Profibus, which were followed by a multitude of other, less generally accepted systems. In the field of electrical installations, the European Installation Bus EIB was generally accepted as a certified, open bus system which can be combined with DDC technology and integrated in in-house control systems. Another technology developed in the USA is the Local Operating Network, LON, whic has a hither transmission rate and higher information content for the various bus members. The contribution compares the two bus systems. [German] Die Einbindung der Kaeltetechnik in die Gebaeudeautomation wird an den Beispielen Lueftungsanlage und Kuehldecke vorgestellt. Die erforderliche Kaelte soll durch einen Kaltwasserersatz energieoptimiert bereitgestellt werden. Dazu muessen Informationen aus dem Verbraucherbereich in der Kaeltezentrale zur Verfuegung stehen. RTL-Anlagen wurden bisher mittels DDC-Technik und firmenspezifischen Bus-Systemen geregelt und gesteuert. Wenn verschiedene Anlagen durch DDC-Systeme unterschiedlicher Hersteller betrieben wurden, so war anfaenglich eine gemeinsame Ueberwachung auf einer zentralen Leitwarte nur ueber Gateways moeglich. Aus der Forderung nach offener Kommunikation unterschiedlicher Systeme entstanden die ersten firmenneutralen Entwicklungen FND und Profibus. Es folgten eine Vielzahl weiterer Netz- und Busdefinitionen und deren Kommunikationsprotokolle, denen jedoch weitgehend eine allgemeine Anerkennung versagt blieb. Im Bereich der Elektroinstallation profilierte sich der

  17. NMC and A and nuclear criticality safety systems integration: A prospective way for enhancement of the nuclear industry facilities safety

    International Nuclear Information System (INIS)

    Ryazanov, Boris G.; Sviridov, Victor I.; Frolov, Vladimir V.; Shvedov, Maxim O.; Mclaughlin, Thomas P.; Pruvost, Norman L.

    2003-01-01

    A considerable body of data has now been acquired about the principles, parameters and consequences of nuclear (criticality) accidents at facilities of the atomic industry in Russia, the United States, Great Britain and Japan. The total number of such accidents stands at 22. Russian and US specialists have prepared a rather extensive survey and analysis of these accidents. The final and important section of this survey is the lessons implied by the results of analysis of these 22 accidents. Among these lessons is the necessity of unconditional enforcement of control over the movement and transformations of special nuclear materials (SNM), and in particular fissile materials, (those SNMs with criticality accident concerns) during production and processing. Inadequacies in such control have been among the causes of most of the accidents that have occurred. Nuclear materials control and accounting (MC and A) for the purpose of ensuring storage reliability and nonproliferation safeguards is a major task of nuclear facilities in any nation. MC and A systems use the latest techniques and hardware for periodic control of SNM in specifically organized material balance areas. Immediate checking, periodic inventory of SNM, and measurements of the parameters of SNM at key points are the main sources of data for these systems. Data about the presence and sites of location of SNM in material balance areas that are acquired in inventories can be used for objective assessment of the status of nuclear safety. On the other hand, the inventory itself involves performance of operations that are unlike routine process engineering, and require special consideration of nuclear safety. Use of the techniques and hardware of MC and A systems not only for purposes of storage reliability, but also to ensure nuclear safety, will reduce the risk of nuclear accidents. This paper gives a concise overview of nuclear accidents that have occurred due to inadequacies in MC and A, and demonstrates

  18. Integration of traditional birth attendants into prevention of mother-to-child transmission at primary health facilities in Kaduna, North-West Nigeria

    Directory of Open Access Journals (Sweden)

    Reward O. Nsirim

    2016-05-01

    Full Text Available One of the fundamental challenges to implementing successful prevention of mother-tochild transmission (PMTCT programs in Nigeria is the uptake of PMTCT services at health facilities. Several issues usually discourage many pregnant women from receiving antenatal care services at designated health facilities within their communities. The CRS Nigeria PMTCT Project funded by the Global Fund in its Round 9 Phase 1 in Nigeria, sought to increase demand for HIV counseling and testing services for pregnant women at 25 supported primary health centers (PHCs in Kaduna State, North-West Nigeria by integrating traditional birth attendants (TBAs across the communities where the PHCs were located into the project. Community dialogues were held with the TBAs, community leaders and women groups. These dialogues focused on modes of mother to child transmission of HIV and the need for TBAs to refer their clients to PHCs for testing. Subsequently, data on number of pregnant women who were counseled, tested and received results was collected on a monthly basis from the 25 facilities using the national HIV/AIDS tools. Prior to this integration, the average number of pregnant women that were counseled, tested and received results was 200 pregnant women across all the 25 health facilities monthly. After the integration of TBAs into the program, the number of pregnant women that were counseled, tested and received results kept increasing month after month up to an average of 1500 pregnant women per month across the 25 health facilities. TBAs can thus play a key role in improving service uptake and utilization for pregnant women at primary health centers in the community – especially in the context of HIV/AIDS. They thus need to be integrated, rather than alienated, from primary healthcare service delivery.

  19. Integration of Traditional Birth Attendants into Prevention of Mother-to-Child Transmission at Primary Health Facilities in Kaduna, North-West Nigeria.

    Science.gov (United States)

    Nsirim, Reward O; Iyongo, Joseph A; Adekugbe, Olayinka; Ugochuku, Maureen

    2015-03-31

    One of the fundamental challenges to implementing successful prevention of mother-to-child transmission (PMTCT) programs in Nigeria is the uptake of PMTCT services at health facilities. Several issues usually discourage many pregnant women from receiving antenatal care services at designated health facilities within their communities. The CRS Nigeria PMTCT Project funded by the Global Fund in its Round 9 Phase 1 in Nigeria, sought to increase demand for HIV counseling and testing services for pregnant women at 25 supported primary health centers (PHCs) in Kaduna State, North-West Nigeria by integrating traditional birth attendants (TBAs) across the communities where the PHCs were located into the project. Community dialogues were held with the TBAs, community leaders and women groups. These dialogues focused on modes of mother to child transmission of HIV and the need for TBAs to refer their clients to PHCs for testing. Subsequently, data on number of pregnant women who were counseled, tested and received results was collected on a monthly basis from the 25 facilities using the national HIV/AIDS tools. Prior to this integration, the average number of pregnant women that were counseled, tested and received results was 200 pregnant women across all the 25 health facilities monthly. After the integration of TBAs into the program, the number of pregnant women that were counseled, tested and received results kept increasing month after month up to an average of 1500 pregnant women per month across the 25 health facilities. TBAs can thus play a key role in improving service uptake and utilization for pregnant women at primary health centers in the community - especially in the context of HIV/AIDS. They thus need to be integrated, rather than alienated, from primary healthcare service delivery.

  20. Pre-test analysis of a LBLOCA using the design data of the ATLAS facility, a reduced-height integral effect test loop for PWRs

    International Nuclear Information System (INIS)

    Hyun-Sik Park; Ki-Yong Choi; Dong-Jin Euh; Tae-Soon Kwon; Won-Pil Baek

    2005-01-01

    Full text of publication follows: The simulation capability of the KAERI integral effect test facility, ATLAS (Advanced Thermalhydraulic Test Loop for Accident Simulation), has been assessed for a large-break loss-of-coolant accident (LBLOCA) transient. The ATLAS facility is a 1/2 height-scaled, 1/144 area-scaled (1/288 in volume scale), and full-pressure test loop based on the design features of the APR1400, an evolutionary pressurized water reactor that has been developed by Korean industry. The APR1400 has four mechanically separated hydraulic trains for the emergency core cooling system (ECCS) with direct vessel injection (DVI). The APR1400 design features have brought about several new safety issues related to the LBLOCA including the steam-water interaction, ECC bypass, and boiling in the reactor vessel downcomer. The ATLAS facility will be used to investigate the multiple responses between the systems or between the components during various anticipated transients. The ATLAS facility has been designed according to a scaling method that is mainly based on the model suggested by Ishii and Kataoka. The ATLAS facility is being evaluated against the prototype plant APR1400 with the same control logics and accident scenarios using the best-estimated code, MARS. This paper briefly introduces the basic design features of the ATLAS facility and presents the results of pre-test analysis for a postulated LBLOCA of a cold leg. The LBLOCA analyses has been conducted to assess the validity of the applied scaling law and the similarity between the ATLAS facility and the APR1400. As the core simulator of the ATLAS facility has the 10% capability of the scaled full power, the blowdown phase can not be simulated, and the starting point of the accident scenario is around the end of blowdown. So it is an important problem to find the correct initial conditions. For the analyzed LBLOCA scenario, the ATLAS facility showed very similar thermal-hydraulic characteristics to the APR

  1. Distributed Energy Resources Test Facility

    Data.gov (United States)

    Federal Laboratory Consortium — NREL's Distributed Energy Resources Test Facility (DERTF) is a working laboratory for interconnection and systems integration testing. This state-of-the-art facility...

  2. Integrated approach to oral health in aged care facilities using oral health practitioners and teledentistry in rural Queensland.

    Science.gov (United States)

    Tynan, Anna; Deeth, Lisa; McKenzie, Debra; Bourke, Carolyn; Stenhouse, Shayne; Pitt, Jacinta; Linneman, Helen

    2018-04-16

    Residents of residential aged care facilities are at very high risk of developing complex oral diseases and dental problems. Key barriers exist in delivering oral health services to residential aged care facilities, particularly in regional and rural areas. A quality improvement study incorporating pre- and post chart audits and pre- and post consultation with key stakeholders, including staff and residents, expert opinion on cost estimates and field notes were used. One regional and three rural residential aged care facilities situated in a non-metropolitan hospital and health service in Queensland. Number of appointments avoided at an oral health facility Feedback on program experience by staff and residents Compliance with oral health care plan implementation Observations of costs involved to deliver new service. The model developed incorporated a visit by an oral health therapist for screening, education, simple intervention and referral for a teledentistry session if required. Results showed an improvement in implementation of oral health care plans and a minimisation of need for residents to attend an oral health care facility. Potential financial and social cost savings for residents and the facilities were also noted. Screening via the oral health therapist and teledentistry appointment minimises the need for a visit to an oral health facility and subsequent disruption to residents in residential aged care facilities. © 2018 National Rural Health Alliance Ltd.

  3. Influence of the heat losses and accumulated heat upon the evolution of the thermohydraulic processes in the transients as applied to the ISB-WWER integral test facility

    International Nuclear Information System (INIS)

    Gashenko, I.V.; Melikhov, O.I.; Shmal, I.I.; Kouznetsov, V.D.

    2001-01-01

    The results of the calculational study using the RELAP5/MOD3.2 thermalhydraulic code performed on the influence of the heat losses to the ambient and the heat accumulated in the pipelines walls upon the evolution of the thermalhydraulic processes in the primary circuit of the integral test facility ISB-WWER when simulating the transients caused by the loss of the coolant are presented in the paper. (authors)

  4. Facility Management in Social Housing: integration of Services for Management of College Student Housing as an opportunity for Supply Development in Italy

    OpenAIRE

    Ernesto Casara; Alberto Fecchio

    2012-01-01

    College Student Residences are construction works for which the State emphasizes the social relevance and disposes facilities for private investors and public operators. Structured transactions by Property Funds are growing since 2007 in order to develop Student Housing. These activities have been changing the Italian Offer Scenery. The proposed model focuses on highquality residential offer and it integrates residence with supports and services in the Student Housing itself. The Provider is ...

  5. Armament Technology Facility (ATF)

    Data.gov (United States)

    Federal Laboratory Consortium — The Armament Technology Facility is a 52,000 square foot, secure and environmentally-safe, integrated small arms and cannon caliber design and evaluation facility....

  6. Covariances of fission-integral measurements at the NBS 252Cf and ISNF facilities and at the ORNL-PCA facility

    International Nuclear Information System (INIS)

    Wagschal, J.J.; Maerker, R.E.; Gilliam, D.M.

    1979-01-01

    Integral measurements together with accompanying uncertainty estimates have been used for the past fifteen years in cross section adjustments. As the field of cross section adjustment came of age, the crude uncertainty estimates were replaced - only in principle, initially - by a quantitative cross section uncertainty covariance description and by uncertainty correlations of integral experiments. There is current interest in the fission reaction rate ratio measurements in the NBS standard neutron fields by people involved in fast reactor cross sections. Also those in the LWR pressure vessel surveillance dosimetry program are interested in these measurements and in similar measurements performed in the Oak Ridge Pool Critical Assembly (PCA). A careful re-examination of uncertainty analysis is presented

  7. Multi-site risk-based project planning, optimization, sequencing and budgeting process and tool for the integrated facility disposition project - 59394

    International Nuclear Information System (INIS)

    Nelson, Jerel; Castillo, Carlos; Huntsman, Julie; Lucek, Heather; Marks, Tim

    2012-01-01

    Document available in abstract form only. Full text of publication follows: Faced with the DOE Complex Transformation, NNSA was tasked with developing an integrated plan for the decommissioning of over 400 facilities and 300 environmental remediation units, as well as the many reconfiguration and modernization projects at the Oak Ridge National Laboratory (ORNL) and Y-12 Complex. Manual scheduling of remediation activities is time-consuming, labor intensive, and inherently introduces bias and unaccounted for aspects of the scheduler or organization in the process. Clearly a tool was needed to develop an objective, unbiased baseline optimized project sequence and schedule with a sound technical foundation for the Integrated Facility Disposition Project (IFDP). In generating an integrated disposition schedule, each project (including facilities, environmental sites, and remedial action units) was identified, characterized, then ranked relative to other projects. Risk matrices allowed for core project data to be extrapolated into probable contamination levels, relative risks to the public, and other technical and risk parameters to be used in the development of an overall ranking. These matrices ultimately generated a complete data set that were used in the Ranking and Sequencing Model (RSM), commonly referred to as the SUPER model, for its numerous abilities to support D and D planning, prioritization, and sequencing

  8. Comparison of three small-break loss-of-coolant accident tests with different break locations using the system-integrated modular advanced reactor-integral test loop facility to estimate the safety of the smart design

    OpenAIRE

    Hwang Bae; Dong Eok Kim; Sung-Uk Ryu; Sung-Jae Yi; Hyun-Sik Park

    2017-01-01

    Three small-break loss-of-coolant accident (SBLOCA) tests with safety injection pumps were carried out using the integral-effect test loop for SMART (System-integrated Modular Advanced ReacTor), i.e., the SMART-ITL facility. The types of break are a safety injection system line break, shutdown cooling system line break, and pressurizer safety valve line break. The thermal–hydraulic phenomena show a traditional behavior to decrease the temperature and pressure whereas the local phenomena are s...

  9. Target Assembly Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Target Assembly Facility integrates new armor concepts into actual armored vehicles. Featuring the capability ofmachining and cutting radioactive materials, it...

  10. The GreenLab Research Facility: A Micro-Grid Integrating Production, Consumption and Storage of Clean Energy

    Science.gov (United States)

    McDowell Bomani, Bilal Mark; Elbuluk, Malik; Fain, Henry; Kankam, Mark D.

    2012-01-01

    There is a large gap between the production and demand for energy from alternative fuel and alternative renewable energy sources. The NASA Glenn Research Center (GRC) has initiated a laboratory-pilot study that concentrates on using biofuels as viable alternative fuel resources for the field of aviation, as well as, utilizing wind and solar technologies as alternative renewable energy resources, and in addition, the use of pumped water for storage of energy that can be retrieved through hydroelectric generation. This paper describes the GreenLab Research Facility and its power and energy sources with .recommendations for worldwide expansion and adoption of the concept of such a facility

  11. An integrated model to measure service management and physical constraints' effect on food consumption in assisted-living facilities.

    Science.gov (United States)

    Huang, Hui-Chun; Shanklin, Carol W

    2008-05-01

    The United States is experiencing remarkable growth in the elderly population, which provides both opportunities and challenges for assisted-living facilities. The objective of this study was to explore how service management influences residents' actual food consumption in assisted-living facilities. Physical factors influencing residents' service evaluation and food consumption also were investigated. A total of 394 questionnaires were distributed to assisted-living residents in seven randomly selected facilities. The questionnaire was developed based on an in-depth literature review and pilot study. Residents' perceived quality evaluations, satisfaction, and physical constraints were measured. Residents' actual food consumption was measured using a plate waste technique. A total of 118 residents in five facilities completed both questionnaires and food consumption assessments. Descriptive, multivariate analyses and structural equation modeling techniques were employed. Service management, including food and service quality and customer satisfaction, was found to significantly influence residents' food consumption. Physical constraints associated with aging, including a decline in health status, chewing problems, sensory loss, and functional disability, also significantly influenced residents' food consumption. A significant relationship was found between physical constraints and customer satisfaction. Foodservice that provides good food and service quality increases customer satisfaction and affects residents' actual food consumption. Physical constraints also influence residents' food consumption directly, or indirectly through satisfaction. The findings suggest that food and nutrition professionals in assisted-living should consider the physical profiles of their residents to enhance residents' satisfaction and nutrient intake. Recommendations for exploring residents' perspectives are discussed.

  12. Integration

    DEFF Research Database (Denmark)

    Emerek, Ruth

    2004-01-01

    Bidraget diskuterer de forskellige intergrationsopfattelse i Danmark - og hvad der kan forstås ved vellykket integration......Bidraget diskuterer de forskellige intergrationsopfattelse i Danmark - og hvad der kan forstås ved vellykket integration...

  13. Integrating the hospital information system (HIS) into the Austrian electronic health record ("ELGA") using the example of the health care facility "Breitenstein".

    Science.gov (United States)

    Bonstingl, Martina

    2014-01-01

    The health care facility "Breitenstein" makes use of a hospital information system to coordinate clinical processes and document medical health data. So as to comply with novel Austrian legislation and fit the "ELGA" architecture, the system has to be adapted. This paper is based on a literature research and gives answers to technical and legal aspects of "ELGA". The introduction of an IHE connector and a CDA manager are the main changes to the current hospital information system. The implementation of interfaces that allow an integration of further "ELGA" features possible are the next step of the project.

  14. Remediation and upgrading of old, inadequate waste management facilities. Integrated waste management system for rare earth and rare metal industry at Sillamaee, Estonia, former uranium facility

    International Nuclear Information System (INIS)

    Kaasik, Tonis; Siinmaa, Anti

    2001-01-01

    discontinuing the use of liquid waste depository and re-arranging completely entire waste management system. One of the most complicated and not yet properly regulated areas is radioactive waste management. The Silmet waste is unique in terms of radioactive waste categorization and applicable regulations. The reason being that its radioactivity levels is above NORM waste but below many TENORM radioactivity levels. How the waste will be treated from a regulatory standpoint has yet to be determined. A conceptual design of Silmet's Integrated Waste Management System defines 'cold top' vitrification technology as the best which converts all hazardous waste and reduces radioactive waste volume by approximately 50% and renders it inert and immobile in the environment. Waste material vitrification involves combining glass-forming compounds with the waste to be treated in a melt chamber heated to a temperature of 950 to 1,350 deg C. Organic compounds within the waste stream are destroyed or encapsulated with the glass matrix. Metals and radionuclides present in the waste are combined within the glass matrix. Unlike solidification/stabilization, which greatly increases final waste volume, this technology significantly reduces the final waste volume, similar to incineration. The resulting glass matrix is the most durable waste form currently known. In fact, the U.S. Environmental Protection Agency has labeled this technology the best demonstrated available technology (BDAT) for high level radioactive waste. (author)

  15. The 10 MWe solar thermal central receiver pilot plant solar facilities design integration, RADL item 1-10

    Science.gov (United States)

    1980-08-01

    Work on the plant support subsystems and engineering services is reported. The master control system, thermal storage subsystem, receiver unit, and the beam characterization system were reviewed. Progress in program management and system integration is highlighted.

  16. Experience on implementation of the Integrated Safeguards approach for the MOX facility from the operator's point of view

    International Nuclear Information System (INIS)

    Nomi, Takayoshi; Nagatani, Taketeru; Ninagawa, Junichi; Nakajima, Shinji; Maruyama, Hajime; Asano, Takashi; Fujiwara, Shigeo

    2011-01-01

    The IS approach for the JNC-1 site was implemented in August 2008, and this was the first experience in the world. This IS approach aimed not only to improve efficiency and effectiveness of safeguards but also to reduce burden of the plant operation by improvement of efficiency of the inspection activity. It was planned to review effectiveness of this new approach after three years from implementation. And JAEA also evaluated effects by application of the IS approach for two MOX fuel facilities in the JNC-1 site based on the three years experiences from the operator's view point. As the result of evaluation, it was confirmed that there were some difference of benefits by application of the IS approach depending on features of the facility, automation level of equipment and advance level of safeguards systems. (author)

  17. The social integration of healthcare agency workers in long-term care facilities: A cross-sectional study.

    Science.gov (United States)

    Lapalme, Marie-Ève; Doucet, Olivier

    2018-06-01

    Patient care quality is a key concern for long-term care facilities and is directly related to effective collaboration between healthcare professionals. The use of agency staff in long-term care facilities creates important challenges in terms of coordination and communication within work units. The purpose of this study is to assess the mediating effect of common in-group identity in the relationship between permanent employees' perceptions regarding the use of agency workers -namely distributive justice, perceptions of threat, perceived similarities with agency workers, and leader inclusiveness toward agency staff- and the permanent employees' adoption of collaborative behaviours. Cross-sectional study. Three long-term care facilities. 290 regular healthcare employees (nurses and care attendants). Data were obtained through questionnaires filled out by employees. Hypotheses were tested using structural equation analyses. The results showed the indirect effects of perceived distributive justice, perceived similarity and leader inclusiveness toward agency workers on permanent employees' cooperation behaviours through common group identification. Perceptions of threat were not related to common group identification or collaborative behaviours. The results also showed that common in-group identification is related to cooperation behaviours only for employees without previous experience as agency workers. This study suggests that permanent healthcare employees who feel they are fairly compensated relative to agency workers, who consider these workers as similar to them, and who believe their supervisor appreciates agency workers' contributions tend to develop a common in-group identity, which fosters collaborative behaviours. Managers of long-term care facilities who wish to foster collaboration among their blended workforce should thus create an environment conducive of a more inclusive identity, particularly if their employees have no previous experience as agency

  18. [Certain medico-economic prerequisites for the integration of spa and resort facilities into the system of compulsory health insurance].

    Science.gov (United States)

    Artem'eva, G B; Gekht, I A

    2013-01-01

    The involvement of spa and resort facilities in the system of compulsory health insurance is of primary importance for the improvement of medical aid provided to the population. The application of the methods for the calculation of differential expenditures on the spa and resort-based treatment and estimation of their dependence on a variety of factors may facilitate the more rational use of the available resources of compulsory health insurance.

  19. [Integrity].

    Science.gov (United States)

    Gómez Rodríguez, Rafael Ángel

    2014-01-01

    To say that someone possesses integrity is to claim that that person is almost predictable about responses to specific situations, that he or she can prudentially judge and to act correctly. There is a closed interrelationship between integrity and autonomy, and the autonomy rests on the deeper moral claim of all humans to integrity of the person. Integrity has two senses of significance for medical ethic: one sense refers to the integrity of the person in the bodily, psychosocial and intellectual elements; and in the second sense, the integrity is the virtue. Another facet of integrity of the person is la integrity of values we cherish and espouse. The physician must be a person of integrity if the integrity of the patient is to be safeguarded. The autonomy has reduced the violations in the past, but the character and virtues of the physician are the ultimate safeguard of autonomy of patient. A field very important in medicine is the scientific research. It is the character of the investigator that determines the moral quality of research. The problem arises when legitimate self-interests are replaced by selfish, particularly when human subjects are involved. The final safeguard of moral quality of research is the character and conscience of the investigator. Teaching must be relevant in the scientific field, but the most effective way to teach virtue ethics is through the example of the a respected scientist.

  20. Experimental Studies for the VVER-440/213 Bubble Condenser System for Kola NPP at the Integral Test Facility BC V-213

    International Nuclear Information System (INIS)

    Blinkov, V.N.; Melikhov, O.I.; Melikhov, V.I.; Davydov, M.V.; Wolff, H.; Arndt, S.

    2012-01-01

    In the frame of Tacis Project R2.01/99, which was running from 2003 to 2005, the bubble condenser system of Kola NPP (unit 3) was qualified at the integral test facility BC V-213. Three LB LOCA tests, two MSLB tests, and one SB LOCA test were performed. The appropriate test scenarios for BC V-213 test facility, modeling accidents in the Kola NPP unit 3, were determined with pretest calculations. Analysis of test results has shown that calculated initial conditions and test scenarios were properly reproduced in the tests. The detailed posttest analysis of the tests performed at BC V-213 test facility was aimed to validate the COCOSYS code for the calculation of thermohydraulic processes in the hermetic compartments and bubble condenser. After that the validated COCOSYS code was applied to NPP calculations for Kola NPP (unit 3). Results of Tacis R2.01/99 Project confirmed the bubble condenser functionality during large and small break LOCAs and MSLB accidents. Maximum loads were reached in the LB LOCA case. No condensation oscillations were observed.

  1. Discharge documentation of patients discharged to subacute facilities: a three-year quality improvement process across an integrated health care system.

    Science.gov (United States)

    Gandara, Esteban; Ungar, Jonathan; Lee, Jason; Chan-Macrae, Myrna; O'Malley, Terrence; Schnipper, Jeffrey L

    2010-06-01

    Effective communication among physicians during hospital discharge is critical to patient care. Partners Healthcare (Boston) has been engaged in a multi-year process to measure and improve the quality of documentation of all patients discharged from its five acute care hospitals to subacute facilities. Partners first engaged stakeholders to develop a consensus set of 12 required data elements for all discharges to subacute facilities. A measurement process was established and later refined. Quality improvement interventions were then initiated to address measured deficiencies and included education of physicians and nurses, improvements in information technology, creation of or improvements in discharge documentation templates, training of hospitalists to serve as role models, feedback to physicians and their service chiefs regarding reviewed cases, and case manager review of documentation before discharge. To measure improvement in quality as a result of these efforts, rates of simultaneous inclusion of all 12 applicable data elements ("defect-free rate") were analyzed over time. Some 3,101 discharge documentation packets of patients discharged to subacute facilities from January 1, 2006, through September 2008 were retrospectively studied. During the 11 monitored quarters, the defect-free rate increased from 65% to 96% (p improvements were seen in documentation of preadmission medication lists, allergies, follow-up, and warfarin information. Institution of rigorous measurement, feedback, and multidisciplinary, multimodal quality improvement processes improved the inclusion of data elements in discharge documentation required for safe hospital discharge across a large integrated health care system.

  2. Design and Integrity Evaluation of High-temperature Piping Systems in the STELLA-2 Sodium Test Facility

    Energy Technology Data Exchange (ETDEWEB)

    Son, Seok-Kwon; Lee, Hyeong-Yeon; Eoh, JaeHyuk; Kim, Jong-Bum; Jeong, Ji-Young [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Ju, Yong-Sun [KOASIS Inc., Daejeon (Korea, Republic of)

    2016-09-15

    In this study, elevated temperature design and integrity evaluation have been conducted using two different piping design codes for the high-temperature piping systems of sodium integral effect test loop for safety simulation and assessment(STELLA-2) being developed by KAERI(Korea Atomic Energy Research Institute). The design code of ASME B31.1 for power piping and French nuclear grade piping design guideline, RCC-MRx RD-3600 were applied, and conservatism of those codes was quantified based on the piping integrity evaluation results. The piping system of Model DHRS, Model IHTS and PSLS are to be installed in STELLA-2. The integrity evaluation results for the three piping systems according to the two design codes showed that integrity of the piping system was confirmed. As a code comparison result, ASME B31.1 was shown to be more conservative for sustained loads while RD-3600 was more conservative for thermal loads compared to B31.1.

  3. Solving a mathematical model integrating unequal-area facilities layout and part scheduling in a cellular manufacturing system by a genetic algorithm.

    Science.gov (United States)

    Ebrahimi, Ahmad; Kia, Reza; Komijan, Alireza Rashidi

    2016-01-01

    In this article, a novel integrated mixed-integer nonlinear programming model is presented for designing a cellular manufacturing system (CMS) considering machine layout and part scheduling problems simultaneously as interrelated decisions. The integrated CMS model is formulated to incorporate several design features including part due date, material handling time, operation sequence, processing time, an intra-cell layout of unequal-area facilities, and part scheduling. The objective function is to minimize makespan, tardiness penalties, and material handling costs of inter-cell and intra-cell movements. Two numerical examples are solved by the Lingo software to illustrate the results obtained by the incorporated features. In order to assess the effects and importance of integration of machine layout and part scheduling in designing a CMS, two approaches, sequentially and concurrent are investigated and the improvement resulted from a concurrent approach is revealed. Also, due to the NP-hardness of the integrated model, an efficient genetic algorithm is designed. As a consequence, computational results of this study indicate that the best solutions found by GA are better than the solutions found by B&B in much less time for both sequential and concurrent approaches. Moreover, the comparisons between the objective function values (OFVs) obtained by sequential and concurrent approaches demonstrate that the OFV improvement is averagely around 17 % by GA and 14 % by B&B.

  4. Integrated five station nondestructive assay system for the support of decontamination and decommissioning of a former plutonium mixed oxide fuel fabrication facility

    International Nuclear Information System (INIS)

    Caldwell, J.T.; Bieri, J.M.; Hastings, R.D.; Horton, W.S.; Kuckertz, T.H.; Kunz, W.E.; Plettenberg, K.; Smith, L.D.

    1990-01-01

    The goal of a safe, efficient and economic decontamination and decommissioning of plutonium facilities can be greatly enhanced through the intelligent use of an integrated system of nondestructive assay equipment. We have designed and fabricated such a system utilizing five separate NDA stations integrated through a single data acquisition and management personal computer-based controller. The initial station utilizes a passive neutron measurement to determine item Pu inventory to the 0.1 gm level prior to insertion into the decontamination cell. A large active neutron station integrated into the cell is used to measure decontamination effectiveness at the 10 nci/gm level. Cell Pu buildup at critical points is monitored with passive neutron detectors. An active neutron station having better than 1 mg Pu assay sensitivity is used to quantify final compacted waste pucks outside the cell. Bulk Pu in various forms and isotopic enrichments is quantified in a combined passive neutron coincidence and high resolution gamma ray spectrometer station outside the cell. Item control and Pu inventory are managed with bar code labeling and a station integrating algorithm. Overall economy is achieved by multiple station use of the same expensive hardware such as the neutron generator

  5. Integrated economics

    International Nuclear Information System (INIS)

    Bratton, T.J.

    1992-01-01

    This article offers ideas for evaluating integrated solid waste management systems through the use of a conceptual cost overview. The topics of the article include the integrated solid waste management system; making assumptions about community characteristics, waste generation rates, waste collection responsibility, integrated system components, sizing and economic life of system facilities, system implementation schedule, facility ownership, and system administration; integrated system costs; integrated system revenues; system financing; cost projections; and making decisions

  6. The integral analysis of 40 mm diameter pipe rupture in cooling system of fusion facility W7-X with ASTEC code

    Energy Technology Data Exchange (ETDEWEB)

    Kačegavičius, Tomas, E-mail: Tomas.Kacegavicius@lei.lt; Povilaitis, Mantas, E-mail: Mantas.Povilaitis@lei.lt

    2015-12-15

    Highlights: • The analysis of loss-of-coolant accident (LOCA) in W7-X facility. • Burst disc is sufficient to prevent pressure inside the plasma vessel exceeding 110 kPa. • Developed model of the cooling system adequately represents the expected phenomena. - Abstract: Fusion is the energy production technology, which could potentially solve problems with growing energy demand of population in the future. Wendelstein 7-X (W7-X) is an experimental facility of stellarator type, which is currently being built at the Max-Planck-Institute for Plasmaphysics located in Greifswald, Germany. W7-X shall demonstrate that in future the energy could be produced in such type of fusion reactors. The safety analysis is required before the operation of the facility could be started. A rupture of 40 mm diameter pipe, which is connected to the divertor unit (module for plasma cooling) to ensure heat removal from the vacuum vessel in case of no-plasma operation mode “baking” is one of the design basis accidents to be investigated. During “baking” mode the vacuum vessel structures and working fluid – water are heated to the temperature 160 °C. This accident was selected for the detailed analysis using integral code ASTEC, which is developed by IRSN (France) and GRS mbH (Germany). This paper presents the integral analysis of W7-X response to a selected accident scenario. The model of the main cooling circuit and “baking” circuit was developed for ASTEC code. There were analysed two cases: (1) rupture of a pipe connected to the upper divertor unit and (2) rupture of a pipe connected to the lower divertor unit. The results of analysis showed that in both cases the water is almost completely released from the units into the plasma vessel. In both cases the pressure in the plasma vessel rapidly increases and in 28 s the set point for burst disc opening is reached preventing further pressurisation.

  7. An integrated analytical framework for quantifying the LCOE of waste-to-energy facilities for a range of greenhouse gas emissions policy and technical factors

    International Nuclear Information System (INIS)

    Townsend, Aaron K.; Webber, Michael E.

    2012-01-01

    This study presents a novel integrated method for considering the economics of waste-to-energy (WTE) facilities with priced greenhouse gas (GHG) emissions based upon technical and economic characteristics of the WTE facility, MSW stream, landfill alternative, and GHG emissions policy. The study demonstrates use of the formulation for six different policy scenarios and explores sensitivity of the results to ranges of certain technical parameters as found in existing literature. The study shows that details of the GHG emissions regulations have large impact on the levelized cost of energy (LCOE) of WTE and that GHG regulations can either increase or decrease the LCOE of WTE depending on policy choices regarding biogenic fractions from combusted waste and emissions from landfills. Important policy considerations are the fraction of the carbon emissions that are priced (i.e. all emissions versus only non-biogenic emissions), whether emissions credits are allowed due to reducing fugitive landfill gas emissions, whether biogenic carbon sequestration in landfills is credited against landfill emissions, and the effectiveness of the landfill gas recovery system where waste would otherwise have been buried. The default landfill gas recovery system effectiveness assumed by much of the industry yields GHG offsets that are very close to the direct non-biogenic GHG emissions from a WTE facility, meaning that small changes in the recovery effectiveness cause relatively larger changes in the emissions factor of the WTE facility. Finally, the economics of WTE are dependent on the MSW stream composition, with paper and wood being advantageous, metal and glass being disadvantageous, and plastics, food, and yard waste being either advantageous or disadvantageous depending upon the avoided tipping fee and the GHG emissions price.

  8. Verification of the code ATHLET by post-test analysis of two experiments performed at the CCTF integral test facility

    International Nuclear Information System (INIS)

    Krepper, E.; Schaefer, F.

    2001-03-01

    In the framework of the external validation of the thermohydraulic code ATHLET Mod 1.2 Cycle C, which has been developed by the GRS, post test analyses of two experiments were done, which were performed at the japanese test facility CCTF. The test facility CCTF is a 1:25 volume-scaled model of a 1000 MW pressurized water reactor. The tests simulate a double end break in the cold leg of the PWR with ECC injection into the cold leg and with combined ECC injection into the hot and cold legs. The evaluation of the calculated results shows, that the main phenomena can be calculated in a good agreement with the experiment. Especially the behaviour of the quench front and the core cooling are calculated very well. Applying a two-channel representation of the reactor model the radial behaviour of the quench front could be reproduced. Deviations between calculations and experiment can be observed simulating the emergency injection in the beginning of the transient. Very high condensation rates were calculated and the pressure decrease in this phase of the transient is overestimated. Besides that, the pressurization due to evaporation in the refill phase is underestimated by ATHLET. (orig.) [de

  9. Comparison of three small-break loss-of-coolant accident tests with different break locations using the system-integrated modular advanced reactor-integral test loop facility to estimate the safety of the smart design

    Directory of Open Access Journals (Sweden)

    Hwang Bae

    2017-08-01

    Full Text Available Three small-break loss-of-coolant accident (SBLOCA tests with safety injection pumps were carried out using the integral-effect test loop for SMART (System-integrated Modular Advanced ReacTor, i.e., the SMART-ITL facility. The types of break are a safety injection system line break, shutdown cooling system line break, and pressurizer safety valve line break. The thermal–hydraulic phenomena show a traditional behavior to decrease the temperature and pressure whereas the local phenomena are slightly different during the early stage of the transient after a break simulation. A safety injection using a high-pressure pump effectively cools down and recovers the inventory of a reactor coolant system. The global trends show reproducible results for an SBLOCA scenario with three different break locations. It was confirmed that the safety injection system is robustly safe enough to protect from a core uncovery.

  10. Comparison of three small-break loss-of-coolant accident tests with different break locations using the system-integrated modular advanced reactor-integral test loop facility to estimate the safety of the smart design

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Hwang; Ryu, Sung Uk; Yi, Sung Jae; Park, Hyun Sik [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Dong Eok [Dept. of Precision Mechanical Engineering, Kyungpook National University, Sangju (Korea, Republic of)

    2017-08-15

    Three small-break loss-of-coolant accident (SBLOCA) tests with safety injection pumps were carried out using the integral-effect test loop for SMART (System-integrated Modular Advanced ReacTor), i.e., the SMART-ITL facility. The types of break are a safety injection system line break, shutdown cooling system line break, and pressurizer safety valve line break. The thermal–hydraulic phenomena show a traditional behavior to decrease the temperature and pressure whereas the local phenomena are slightly different during the early stage of the transient after a break simulation. A safety injection using a high-pressure pump effectively cools down and recovers the inventory of a reactor coolant system. The global trends show reproducible results for an SBLOCA scenario with three different break locations. It was confirmed that the safety injection system is robustly safe enough to protect from a core uncovery.

  11. Use of an integrated human health/ecological risk assessment to develop a long-term groundwater/site management plan for a sour gas facility

    International Nuclear Information System (INIS)

    Swanson, S.M.; Shaw, R.D.; McClymont, G.; Nadeau, S.

    1995-01-01

    An integrated human health and ecological risk assessment was used to quantify the level of risk associated with the off-site movement of contaminants via groundwater and soils at a medium-sized gas processing facility in southern Alberta. The study incorporated three key aspects: (1) integration; (2) consultation; and, (3) pro-active remedial actions. Integration was complete, beginning with the Problem Formulation stage and progressing through Risk Characterization and Risk Management. This integration was reflected in a multidisciplinary team of hydrogeologists, biologists and human health specialists. Several lessons emerged from the integrated approach: (1) spending 2/3 of the time and resources on Problem Formulation prevented later problems; (2) the different perspectives provided by the various specialists helped reveal the relative importance of pathways and ecological receptors (3) clear, consistent screening procedures for contaminants of concern and receptors were very effective with stakeholders; (4) exposure scenarios that incorporated common-sense situations (although still conservative) contributed to the credibility of the risk analysis; and, (5) an innovative combination of toxicity testing and chemical analysis helped delineate the boundaries of the potentially contaminated area for both human and ecological receptors in a cost effective manner. Consultation included directly affected parties, regulatory personnel and community members. The consultation extended through the project, with key ''buy-in'' points during Problem Formulation and Risk Characterization/Management. Pro-active remedial action included the removal of contaminant sources in the 1980's, a pump-and-treat system and extensive monitoring. These actions showed commitment and set the stage for credible risk-based mitigation and long-term monitoring

  12. Integration of the nuclear energy among the production facilities of energy in France; Integration de l'energie nucleaire parmi les moyens de production de l'energie en france

    Energy Technology Data Exchange (ETDEWEB)

    Ailleret, P [Electricite de France (EDF), 75 - Paris (France). Direction des Etudes et Recherches; Taranger, P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1955-07-01

    The present report gives an overview of the present facilities of energy productions in France and their perspectives. the electric production comes for half about power stations hydraulics and for half of thermal power stations. However due to the increase of the energy consumption, France is particularly interested by the atomic energy that appears to bring a supply in due time to the hydraulics and to limit a development of the thermal power stations to which the natural resources of France in classic fuel would not permit to cope presumably. The integration of the nuclear plants to the other production facilities will make itself gradually according to the evolution of the energy needs. (M.B.) [French] Le present rapport donne un apercu des moyens actuels de productions energetiques en France et de ses perspectives. la production electrique provient pour moitie environ de centrales hydraulique et pour moitie de centrales thermiques. Cependant face a l'augmentation de la consommation energetique, la France est tres particulierement interessee par l'energie atomique qui parait devoir apporter en temps utile la releve a l'hydraulique et limiter un developpement des centrales thermiques auxquels les ressources naturelles de la France en combustible classique ne permettraient vraisemblablement pas de faire face. L'integration des centrales nucleaires aux autres moyens de production se fera graduellment en fonction de l'evolution des besoins energetiques. (M.B.)

  13. Evaluation of energy efficiency options in steam assisted gravity drainage oil sands surface facilities via process integration

    International Nuclear Information System (INIS)

    Carreon, Carlos E.; Mahmoudkhani, Maryam; Alva-Argaez, Alberto; Bergerson, Joule

    2015-01-01

    While new technologies are being developed for extracting unconventional oil, in the near term economic benefits and footprint reduction can be achieved by enhancing the energy efficiency of existing facilities. The objective of this work is to evaluate energy efficiency opportunities for in situ extraction of Canada's oil sands resource using pinch analysis. Modifications to an original plant design are analyzed in order to estimate utility savings beyond those obtained for the initial process configuration. The modifications explored in this paper are estimated to deliver energy savings of up to 6% beyond ‘business as usual’. This corresponds to GHG emissions reduction of approximately 5%. However, in some cases, this increase in energy savings comes at the cost of increasing demand for make-up water and volume of disposal water. Surplus generation of steam beyond heating requirements in the water treatment system leads to energy inefficiencies. Additional cost and energy savings are obtained by reducing or eliminating the use of glycol in the cooling circuit. - Highlights: • Pinch analysis performed for unconventional oil recovery process to identify inefficiencies. • Both the removal of pinch violations and process modifications lead to savings. • Effect of energy savings on water consumption for the process is considered. • Greenhouse gas emissions reduction and economic benefit are estimated for the studied cases

  14. Integrating cut-and-solve and semi-Lagrangean based dual ascent for the single-source capacitated facility location problem

    DEFF Research Database (Denmark)

    Gadegaard, Sune Lauth

    polytope with generalized upper bounds. From our computational study, we show that the semi-Lagrangean relaxation approach has its merits when the instances are tightly constrained with regards to the capacity of the system, but that it is very hard to compete with a standalone implementation of the cut......This paper describes how the cut-and-solve framework and semi-Lagrangean based dual ascent algorithms can be integrated in two natural ways in order to solve the single source capacitated facility location problem. The first uses the cut-and-solve framework both as a heuristic and as an exact...... solver for the semi-Lagrangean subproblems. The other uses a semi-Lagrangean based dual ascent algorithm to solve the sparse problems arising in the cut-and-solve algorithm. Furthermore, we developed a simple way to separate a special type of cutting planes from what we denote the effective capacity...

  15. Steam condensation induced water hammer in a vertical up-fill configuration within an integral test facility. Experiments and computational simulations

    Energy Technology Data Exchange (ETDEWEB)

    Dirndorfer, Stefan

    2017-01-17

    Condensation induced water hammer is a source of danger and unpredictable loads in pipe systems. Studies concerning condensation induced water hammer were predominantly made for horizontal pipes, studies concerning vertical pipe geometries are quite rare. This work presents a new integral test facility and an analysis of condensation induced water hammer in a vertical up-fill configuration. Thanks to the state of the art technology, the phenomenology of vertical condensation induced water hammer can be analysed by means of sufficient high-sampled experimental data. The system code ATHLET is used to simulate UniBw condensation induced water hammer experiments. A newly developed and implemented direct contact condensation model enables ATHLET to calculate condensation induced water hammer. Selected experiments are validated by the modified ATHLET system code. A sensitivity analysis in ATHLET, together with the experimental data, allows to assess the performance of ATHLET to compute condensation induced water hammer in a vertical up-fill configuration.

  16. Steam condensation induced water hammer in a vertical up-fill configuration within an integral test facility. Experiments and computational simulations

    International Nuclear Information System (INIS)

    Dirndorfer, Stefan

    2017-01-01

    Condensation induced water hammer is a source of danger and unpredictable loads in pipe systems. Studies concerning condensation induced water hammer were predominantly made for horizontal pipes, studies concerning vertical pipe geometries are quite rare. This work presents a new integral test facility and an analysis of condensation induced water hammer in a vertical up-fill configuration. Thanks to the state of the art technology, the phenomenology of vertical condensation induced water hammer can be analysed by means of sufficient high-sampled experimental data. The system code ATHLET is used to simulate UniBw condensation induced water hammer experiments. A newly developed and implemented direct contact condensation model enables ATHLET to calculate condensation induced water hammer. Selected experiments are validated by the modified ATHLET system code. A sensitivity analysis in ATHLET, together with the experimental data, allows to assess the performance of ATHLET to compute condensation induced water hammer in a vertical up-fill configuration.

  17. The Self-Calibration Test of flowmeter installed in STELLA(Sodium Integral Effect Test Loop for Safety Simulation and Assessment) facility

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Minhwan; Jeong, Ji-Young [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The objective of this study is to describe the procedure of the self-calibration test for the flowmeters and to analyze the result of the test. In this work, the test procedure of the self-calibration of two flowmeters (FT-101, FT-102) installed in STELLA facility was described and the test result was analyzed. In regard to the long-term SFR development plan, a large-scale sodium thermal-hydraulic test project is being progressed by KAERI. This project is called STELLA (Sodium Integral Effect Test Loop for Safety Simulation and Assessment), and it is proceeding by adopting the QA (Quality Assurance) program. Due to the specificity of an experiment using sodium(Na) categorized as Class 3(pyrophoric material and water-prohibiting substance) by the Safety Control of Dangerous Substances Act, it is necessary to apply QA in consideration of the sodium experiment environment in certain parts. The one of them is about calibration of measuring instrument such as a flowmeter, thermocouple and pressure gauge. It is described in the QAP (Quality Assurance Procedures) of KAERI that calibration work should be conducted in accordance with self-calibration procedures in a special case where conventional calibration is not practicable. The calibration of two flowmeters (FT-101, FT-102) installed in STELLA facility is the typical example. As a result of test, it was confirmed that the flowmeters meet the pass criterion. Therefore, it was concluded that the flowmeters maintain instrument capacity a year ago.

  18. Mountain Home Geothermal Project: geothermal energy applications in an integrated livestock meat and feed production facility at Mountain Home, Idaho. [Contains glossary

    Energy Technology Data Exchange (ETDEWEB)

    Longyear, A.B.; Brink, W.R.; Fisher, L.A.; Matherson, R.H.; Neilson, J.A.; Sanyal, S.K.

    1979-02-01

    The Mountain Home Geothermal Project is an engineering and economic study of a vertically integrated livestock meat and feed production facility utilizing direct geothermal energy from the KGRA (Known Geothermal Resource Area) southeast of Mountain Home, Idaho. A system of feed production, swine raising, slaughter, potato processing and waste management was selected for study based upon market trends, regional practices, available technology, use of commercial hardware, resource characteristics, thermal cascade and mass flow considerations, and input from the Advisory Board. The complex covers 160 acres; utilizes 115 million Btu per hour (34 megawatts-thermal) of geothermal heat between 300/sup 0/F and 70/sup 0/F; has an installed capital of $35.5 million;produces 150,000 hogs per year, 28 million lbs. of processed potatoes per year, and on the order of 1000 continuous horsepower from methane. The total effluent is 200 gallons per minute (gpm) of irrigation water and 7300 tons per year of saleable high grade fertilizer. The entire facility utilizes 1000 gpm of 350/sup 0/F geothermal water. The economic analysis indicates that the complex should have a payout of owner-invested capital of just over three years. Total debt at 11% per year interest would be paid out in 12 (twelve) years.

  19. Quality of nutrition services in primary health care facilities: Implications for integrating nutrition into the health system in Bangladesh.

    Directory of Open Access Journals (Sweden)

    Sk Masum Billah

    Full Text Available In 2011, the Bangladesh Government introduced the National Nutrition Services (NNS by leveraging the existing health infrastructure to deliver nutrition services to pregnant woman and children. This study examined the quality of nutrition services provided during antenatal care (ANC and management of sick children younger than five years.Service delivery quality was assessed across three dimensions; structural readiness, process and outcome. Structural readiness was assessed by observing the presence of equipment, guidelines and register/reporting forms in ANC rooms and consulting areas for sick children at 37 primary healthcare facilities in 12 sub-districts. In addition, the training and knowledge relevant to nutrition service delivery of 95 healthcare providers was determined. The process of nutrition service delivery was assessed by observing 381 ANC visits and 826 sick children consultations. Satisfaction with the service was the outcome and was determined by interviewing 541 mothers/caregivers of sick children.Structural readiness to provide nutrition services was higher for ANC compared to management of sick children; 73% of ANC rooms had >5 of the 13 essential items while only 13% of the designated areas for management of sick children had >5 of the 13 essential items. One in five (19% healthcare providers had received nutrition training through the NNS. Delivery of the nutrition services was poor: <30% of women received all four key antenatal nutrition services, 25% of sick children had their weight checked against a growth-chart and <1% had their height measured. Nevertheless, most mothers/caregivers rated their satisfaction of the service above average.Strengthening the provision of equipment and increasing the coverage of training are imperative to improve nutrition services. Inherent barriers to implementing nutrition services in primary health care, especially high caseloads during the management of sick under-five children, should

  20. PWR-related integral safety experiments in the PKL 111 test facility SBLOCA under beyond-design-basis accident conditions

    Energy Technology Data Exchange (ETDEWEB)

    Weber, P.; Umminger, K.J.; Schoen, B. [Siemens AG Power Generation Group (KWU), Erlangen (France)

    1995-09-01

    The thermal hydraulic behavior of a PWR during beyond-design-basis accident scenarios is of vital interest for the verification and optimization of accident management procedures. Within the scope of the German reactor safety research program experiments were performed in the volumetrically scaled PKL 111 test facility by Siemens/KWU. This highly instrumented test rig simulates a KWU-design PWR (1300 MWe). In particular, the latest tests performed related to a SBLOCA with additional system failures, e.g. nitrogen entering the primary system. In the case of a SBLOCA, it is the goal of the operator to put the plant in a condition where the decay heat can be removed first using the low pressure emergency core cooling system and then the residual heat removal system. The experimental investigation presented assumed the following beyond-design-basis accident conditions: 0.5% break in a cold leg, 2 of 4 steam generators (SGs) isolated on the secondary side (feedwater- and steam line-valves closed), filled with steam on the primary side, cooldown of the primary system using the remaining two steam generators, high pressure injection system only in the two loops with intact steam generators, if possible no operator actions to reach the conditions for residual heat removal system activation. Furthermore, it was postulated that 2 of the 4 hot leg accumulators had a reduced initial water inventory (increased nitrogen inventory), allowing nitrogen to enter the primary system at a pressure of 15 bar and nearly preventing the heat transfer in the SGs ({open_quotes}passivating{close_quotes} U-tubes). Due to this the heat transfer regime in the intact steam generators changed remarkably. The primary system showed self-regulating system effects and heat transfer improved again (reflux-condenser mode in the U-tube inlet region).

  1. Integration of TB-HIV services at an ANC facility in Frances Baard District, Northern Cape, South Africa.

    Science.gov (United States)

    Peters, J A; Heunis, C; Kigozi, G; Osoba, T; van der Walt, M

    2015-03-21

    Integrated tuberculosis-human immunodeficiency virus (TB-HIV) service delivery as part of maternal health services, including antenatal care (ANC), is widely recommended. This study assessed the implementation of collaborative TB-HIV service delivery at a hospital-based ANC service unit. A record review of a random sample of 308 pregnant women attending the ANC service between April 2011 and February 2012 was conducted. Data were extracted from registers and patient case notes. Outcomes included the proportion of women who underwent HIV counselling and testing (HCT), CD4 count testing, antiretroviral treatment (ART), cotrimoxazole preventive treatment (CPT), TB screening and isoniazid preventive treatment (IPT). Analysis measured variations in patient characteristics associated with service delivery. All women underwent HCT; 80% of those who tested HIV-positive were screened for TB. Most (85.9%) of the HIV-positive women received a CD4 count. However, only 12.9% of eligible women received ART prophylaxis onsite, only 35.7% were referred for initiation of ART, only 42.3% commenced IPT and none received CPT or further investigations for TB. HIV-negative women had 2.6 higher odds (95%CI 1.3-5.3) of receiving TB screening than their HIV-positive counterparts. Although the identification of HIV-positive women and TB suspects was adequate, implementation of other TB-HIV collaborative activities was sub-optimal.

  2. Facile fabrication of Ag dendrite-integrated anodic aluminum oxide membrane as effective three-dimensional SERS substrate

    Science.gov (United States)

    Zhang, Cong-yun; Lu, Ya; Zhao, Bin; Hao, Yao-wu; Liu, Ya-qing

    2016-07-01

    A novel surface enhanced Raman scattering (SERS)-active substrate has been successfully developed, where Ag-dendrites are assembled on the surface and embedded in the channels of anodic aluminum oxide (AAO) membrane, via electrodeposition in AgNO3/PVP aqueous system. Reaction conditions were systematically investigated to attain the best Raman enhancement. The growth mechanism of Ag dendritic nanostructures has been proposed. The Ag dendrite-integrated AAO membrane with unique hierarchical structures exhibits high SERS activity for detecting rhodamine 6G with a detection limit as low as 1 × 10-11 M. Furthermore, the three-dimensional (3D) substrates display a good reproducibility with the average intensity variations at the major Raman peak less than 12%. Most importantly, the 3D SERS substrates without any surface modification show an outstanding SERS response for the molecules with weak affinity for noble metal surfaces. The potential application for the detection of polycyclic aromatic hydrocarbons (PAHs) was evaluated with fluoranthene as Raman target molecule and a sensitive SERS detection with a limit down to 10-8 M was reached. The 3D SERS-active substrate shows promising potential for rapid detection of trace organic pollutants even weak affinity molecules in the environment.

  3. Advanced Microanalysis Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Advanced Microanalysis Facility fully integrates capabilities for chemical and structural analysis of electronic materials and devices for the U.S. Army and DoD....

  4. Economics of reusable facilities

    International Nuclear Information System (INIS)

    Antia, D.D.J.

    1992-01-01

    In this paper some of the different economic development strategies that can be used for reusable facilities in the UK, Norway, Netherlands and in some production sharing contracts are outlined. These strategies focus on an integrated decision analysis approach which considers development phasing, reservoir management, tax planning and where appropriate facility purchase, leasing, or sale and leaseback decisions

  5. 'Integration'

    DEFF Research Database (Denmark)

    Olwig, Karen Fog

    2011-01-01

    , while the countries have adopted disparate policies and ideologies, differences in the actual treatment and attitudes towards immigrants and refugees in everyday life are less clear, due to parallel integration programmes based on strong similarities in the welfare systems and in cultural notions...... of equality in the three societies. Finally, it shows that family relations play a central role in immigrants’ and refugees’ establishment of a new life in the receiving societies, even though the welfare society takes on many of the social and economic functions of the family....

  6. Structural integrity of heavy liquid-metal target installed in spallation neutron facility. Part 4: Consideration by fracture mechanics of target container window

    International Nuclear Information System (INIS)

    Ishikura, Syuichi; Kogawa, Hiroyuki; Futakawa, Masatoshi; Kikuchi, Kenji; Haga, Katsuhiro; Kaminaga, Masanori; Hino, Ryutaro

    2004-01-01

    Developments of the neutron scattering facility is carried out under the high-intensity proton accelerator project promoted by JAERI and KEK. To estimate the structural integrity of the heavy liquid-metal (mercury) target used as a spallation neutron source in a MW-class neutron scattering facility, static and dynamic stress (including pressure wave in mercury) behaviors due to the incident of 1MW-pulsed proton beam (Maximum heat density is 461W/cc) were analyzed. In the analyses, two type target containers with semi-cylindrical type and flat-type beam windows were used as analytical models. As a result, it is confirmed that the stress generated by the pressure wave becomes the largest at the center of the beam window, and the flat-type beam window is more advantageous from the structural viewpoint than the semi-cylindrical type beam window. It has been understood that the stress generated in the beam window by the pressure wave can be treated as the secondary stress. Then, it has been understood that the stress and the stress range generated in the target window were bellow the allowable stress level defined by the standard of JIS on the maximum stress and fatigue strength. It has been experimentally confirmed that a cavitation was generated by generating the negative pressure in mercury near the target beam window and a collapse of cavitation damaged to the target container material, as pits. Then, the fracture mechanical analyses were carried out on the pit and a crack on pit tip. Consequently, it was clarified that the crack would not propagate because the inner surface of the beam window was become the compressive stress field due to the steady state thermal stress. Moreover, the evaluation technique of the cavitation which would be needed in the future was summarized. (author)

  7. Development of N_2O-MTV for low-speed flow and in-situ deployment to an integral effect test facility

    Science.gov (United States)

    André, Matthieu A.; Burns, Ross A.; Danehy, Paul M.; Cadell, Seth R.; Woods, Brian G.; Bardet, Philippe M.

    2018-01-01

    A molecular tagging velocity (MTV) technique is developed to non-intrusively measure velocity in an integral effect test (IET) facility simulating a high-temperature helium-cooled nuclear reactor in accident scenarios. In these scenarios, the velocities are expected to be low, on the order of 1 m/s or less, which forces special requirements on the MTV tracer selection. Nitrous oxide (N_2O) is identified as a suitable seed gas to generate NO tracers capable of probing the flow over a large range of pressure, temperature, and flow velocity. The performance of N_2O-MTV is assessed in the laboratory at temperature and pressure ranging from 295 to 781 K and 1 to 3 atm. MTV signal improves with a temperature increase, but decreases with a pressure increase. Velocity precision down to 0.004 m/s is achieved with a probe time of 40 ms at ambient pressure and temperature. Measurement precision is limited by tracer diffusion, and absorption of the tag laser beam by the seed gas. Processing by cross-correlation of single-shot images with high signal-to-noise ratio reference images improves the precision by about 10% compared to traditional single-shot image correlations. The instrument is then deployed to the IET facility. Challenges associated with heat, vibrations, safety, beam delivery, and imaging are addressed in order to successfully operate this sensitive instrument in-situ. Data are presented for an isothermal depressurized conduction cooldown. Velocity profiles from MTV reveal a complex flow transient driven by buoyancy, diffusion, and instability taking place over short (30 min) time scales at sub-meter per second speed. The precision of the in-situ results is estimated at 0.027, 0.0095, and 0.006 m/s for a probe time of 5, 15, and 35 ms, respectively.

  8. Vehicle Thermal Management Facilities | Transportation Research | NREL

    Science.gov (United States)

    Integration Facility The Vehicle Testing and Integration Facility features a pad to conduct vehicle thermal station next to the pad provides a continuous data stream on temperature, humidity, wind speed, and solar

  9. Design, fabrication, installation and shielding integrity testing of source storage container for automatic source movement system used in TLD calibration facility

    International Nuclear Information System (INIS)

    Subramanian, V.; Baskar, S.; Annalakshmi, O.; Jose, M.T.; Jayshree, C.P.; Choudry, Shreelatha

    2012-01-01

    A state-of-art TLD laboratory has been commissioned in January 2000 at Radiological Safety Division of Indira Gandhi Centre for Atomic Research (IGCAR). The laboratory provides personnel monitoring service to 2000 occupational workers from Indira Gandhi Centre for Atomic Research and Bhabha Atomic Research Centre facilities. The laboratory has been accredited by the Radiation Safety Systems Division (RSSD), Bhabha Atomic Research Centre (BARC) since year 2002. The laboratory has exclusive facility for the calibration of the TLD cards. As apart of accreditation procedure and taking into account of geometry effect, the dose rate at the card position is determined by the accreditation authorities by using graphite chamber (secondary or national standard instrument) and often re estimated by a condenser R meter (M/s Victoreen, Germany) by our laboratory. As per the regulatory requirement, the exposure protocols should be automated. Towards this an automatic source movement system has been augmented in the calibration facility. By using the system, the source will be brought to the irradiation position by pneumatically and exposures will be terminated by counter, timer and triggering system. To accomplish this task a lead container has been designed, fabricated and mounted at the beneath of the calibration table for the storage of source. As per the automation process, a lead container for the source storage has been designed and installed beneath to the Calibration Table. The container was designed to hold a 3Ci 137 Cs source, but present activity of the source is 1.2Ci. Hence, the shielding integrity was tested with higher active source (1.7Ci 60 Co). The dose rate measured outside on the circumference of the container at the middle of the source is found to be the same as calculated using QAD CGGP calculations. The top plug is so designed to avoid inadvertent upward movement of the source. Though, the shielding was not adequate on top of the top plug, however it does

  10. Supply-side dimensions and dynamics of integrating HIV testing and counselling into routine antenatal care: a facility assessment from Morogoro Region, Tanzania.

    Science.gov (United States)

    An, Selena J; George, Asha S; LeFevre, Amnesty E; Mpembeni, Rose; Mosha, Idda; Mohan, Diwakar; Yang, Ann; Chebet, Joy; Lipingu, Chrisostom; Baqui, Abdullah H; Killewo, Japhet; Winch, Peter J; Kilewo, Charles

    2015-10-04

    Integration of HIV into RMNCH (reproductive, maternal, newborn and child health) services is an important process addressing the disproportionate burden of HIV among mothers and children in sub-Saharan Africa. We assess the structural inputs and processes of care that support HIV testing and counselling in routine antenatal care to understand supply-side dynamics critical to scaling up further integration of HIV into RMNCH services prior to recent changes in HIV policy in Tanzania. This study, as a part of a maternal and newborn health program evaluation in Morogoro Region, Tanzania, drew from an assessment of health centers with 18 facility checklists, 65 quantitative and 57 qualitative provider interviews, and 203 antenatal care observations. Descriptive analyses were performed with quantitative data using Stata 12.0, and qualitative data were analyzed thematically with data managed by Atlas.ti. Limitations in structural inputs, such as infrastructure, supplies, and staffing, constrain the potential for integration of HIV testing and counselling into routine antenatal care services. While assessment of infrastructure, including waiting areas, appeared adequate, long queues and small rooms made private and confidential HIV testing and counselling difficult for individual women. Unreliable stocks of HIV test kits, essential medicines, and infection prevention equipment also had implications for provider-patient relationships, with reported decreases in women's care seeking at health centers. In addition, low staffing levels were reported to increase workloads and lower motivation for health workers. Despite adequate knowledge of counselling messages, antenatal counselling sessions were brief with incomplete messages conveyed to pregnant women. In addition, coping mechanisms, such as scheduling of clinical activities on different days, limited service availability. Antenatal care is a strategic entry point for the delivery of critical tests and counselling messages

  11. Surplus Facilities Management Program

    International Nuclear Information System (INIS)

    Coobs, J.H.

    1983-01-01

    This is the second of two programs that are concerned with the management of surplus facilities. The facilities in this program are those related to commercial activities, which include the three surplus experimental and test reactors [(MSRE, HRE-2, and the Low Intensity Test Reactor (LITR)] and seven experimental loops at the ORR. The program is an integral part of the Surplus Facilities Management Program, which is a national program administered for DOE by the Richland Operations Office. Very briefly reported here are routine surveillance and maintenance of surplus radioactively contaminated DOE facilities awaiting decommissioning

  12. Facilities & Leadership

    Data.gov (United States)

    Department of Veterans Affairs — The facilities web service provides VA facility information. The VA facilities locator is a feature that is available across the enterprise, on any webpage, for the...

  13. Integral measurements of lattice properties in the natural uranium-graphite critical facility Marius; Mesures globales de reseaux a graphite dans l'empilement critique marius

    Energy Technology Data Exchange (ETDEWEB)

    Cogne, F [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    A systematic study of natural uranium-graphite lattices has been undertaken in the critical facility MARIUS, which was built in 1959 in Marcoule. Integral measurement of lattice properties are carried out by the progressive replacement method. This report describes the experimental methods, the analysis of the experiments and the results obtained for lattices with pitches ranging from 192 to 317 mm and fuel elements with cross sections ranging from 6 to 20 cm{sup 2}. The principles of correlation of the results are also outlined. Additional experimental results are also given, pertaining to the determination of the anisotropy, of both the axial and the radial migration areas, and of the age in graphite. (author) [French] L'empilement critique MARIUS, construit en 1959 a Marcoule, a ete utilise pour l'etude systematique des reseaux a graphite-uranium naturel. Les mesures globales de reseaux sont faites par la methode de remplacement progressif. On decrit ici les methodes experimentales utilisees pour ces mesures globales, les principes du depouillement et les resultats obtenus pour des pas de 192 a 317 mm et des combustibles de 6 a 20 cm{sup 2} d'uranium naturel. On donne d'autre part le principe de correlation des mesures. Un certain nombre de resultats experimentaux complementaires sont donnes, en permettant de determiner l'anisotropie, les aires de migration axiale et radiale, l'age dans le graphite. (auteur)

  14. Biochemistry Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Biochemistry Facility provides expert services and consultation in biochemical enzyme assays and protein purification. The facility currently features 1) Liquid...

  15. Missile/Munition Integration Facility

    Data.gov (United States)

    Federal Laboratory Consortium — A large complex contained within approximately 600 acres with security fencing, controlled access gates, and a munitions convoy access road. The complex is capable...

  16. A study on the methodology of integrated safety assessment on low and intermediate level waste (LILW) managed in temporary storage facility at NPP

    International Nuclear Information System (INIS)

    Ahn, Min Ho

    2010-02-01

    Since 1978, the KHNP has been operating 20 NPPs (16 PWRs and 4 CANDUs) and generating about 67,000 drums (200 L) of LILW (as of December 31, 2005), which have been stored in the temporary storage facility (TSF) at each NPP due to the absence of a repository for the disposal of LILW. Therefore, the period of temporary storage of LILW is so long compared to other countries. Furthermore, the details with respect to the safety analyse on the TSF have not been considered in PSAR and FSAR. Especially, the risk assessment on the TSF has scarcely been conducted as opposed to many researches on the disposal of LILW. Since 2003, however, the IAEA has been recognized on the importance of predispoal management of LILW. And then, the regulatory frame of U.S. NRC was being shifted to risk-based regulation from the deterministic approach. Therefore, most of radioactive wastes including the LILW will be managed in terms of the risk-based graded approach to future regulation system called RIR (risk informed regulation). If the radioactive wastes do not quantitatively deal with the risk-based regulation, the radiological risk on some of radioactive wastes might be overestimated or underestimated regardless of the degree of the risk. According to a consequence of these situations, the numbers of the researches on the predisposal management of LILW have been required for the preparation on new regulatory frame. In this study, the main objective of this study is to establish the methodology of integrated safety assessment on LILW managed in the TSF at NPP, and to develop the integrated safety assessment code for routine operating condition and for for accident analysis on LILW managed in the TSF. In order to establish the methodology of integrated safety assessment on LILW managed in the TSF at NPP, three main parameters were considered: risk-based accident scenarios, radionuclide inventory, and atmospheric dispersion factor (χ/Q). Arbitrary accidents related to LILW management in the

  17. Dance Facilities.

    Science.gov (United States)

    Ashton, Dudley, Ed.; Irey, Charlotte, Ed.

    This booklet represents an effort to assist teachers and administrators in the professional planning of dance facilities and equipment. Three chapters present the history of dance facilities, provide recommended dance facilities and equipment, and offer some adaptations of dance facilities and equipment, for elementary, secondary and college level…

  18. Technical Approach for Determining Key Parameters Needed for Modeling the Performance of Cast Stone for the Integrated Disposal Facility Performance Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Yabusaki, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Serne, R. Jeffrey [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Rockhold, Mark L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wang, Guohui [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Westsik, Joseph H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-03-30

    Washington River Protection Solutions (WRPS) and its contractors at Pacific Northwest National Laboratory (PNNL) and Savannah River National Laboratory (SRNL) are conducting a development program to develop / refine the cementitious waste form for the wastes treated at the ETF and to provide the data needed to support the IDF PA. This technical approach document is intended to provide guidance to the cementitious waste form development program with respect to the waste form characterization and testing information needed to support the IDF PA. At the time of the preparation of this technical approach document, the IDF PA effort is just getting started and the approach to analyze the performance of the cementitious waste form has not been determined. Therefore, this document looks at a number of different approaches for evaluating the waste form performance and describes the testing needed to provide data for each approach. Though the approach addresses a cementitious secondary aqueous waste form, it is applicable to other waste forms such as Cast Stone for supplemental immobilization of Hanford LAW. The performance of Cast Stone as a physical and chemical barrier to the release of contaminants of concern (COCs) from solidification of Hanford liquid low activity waste (LAW) and secondary wastes processed through the Effluent Treatment Facility (ETF) is of critical importance to the Hanford Integrated Disposal Facility (IDF) total system performance assessment (TSPA). The effectiveness of cementitious waste forms as a barrier to COC release is expected to evolve with time. PA modeling must therefore anticipate and address processes, properties, and conditions that alter the physical and chemical controls on COC transport in the cementitious waste forms over time. Most organizations responsible for disposal facility operation and their regulators support an iterative hierarchical safety/performance assessment approach with a general philosophy that modeling provides

  19. Development of a qualified nodalization for small-break LOCA transient analysis in PSB-VVER integral test facility by RELAP5 system code

    Energy Technology Data Exchange (ETDEWEB)

    Shahedi, S. [Department of Energy Engineering, Sharif University of Technology, Azadi Street, Tehran (Iran, Islamic Republic of); Jafari, J., E-mail: jalil_jafari@yahoo.co [Reactors and Accelerators R and D School, Nuclear Science and Technology Research Institute, North Kargar Street, Tehran (Iran, Islamic Republic of); Boroushaki, M. [Department of Energy Engineering, Sharif University of Technology, Azadi Street, Tehran (Iran, Islamic Republic of); D' Auria, F. [DIMNP, University of Pisa, Via Diotisalvi 2, 56126 Pisa (Italy)

    2010-10-15

    This paper deals with development and qualification of a nodalization for modeling of the PSB-VVER integral test facility (ITF) by RELAP5/MOD3.2 code and prediction of its primary and secondary systems behaviors at steady state and transient conditions. The PSB-VVER is a full-height, 1/300 volume and power scale representation of a VVER-1000 NPP. A RELAP5 nodalization has been developed for PSB-VVER modeling and a nodalization qualification process has been applied for the developed nodalization at steady state and transient levels and a qualified nodalization has been proposed for modeling of the PSB ITF. The 11% small-break loss-of-coolant-accident (SBLOCA), i.e. rupture of one of the hydroaccumulators (HA) injection lines in the upper plenum (UP) region of reactor pressure vessel (RPV) below the hot legs (HL), inlets has been considered for nodalization qualification process. The influence of the different steam generator (SG) nodalizations on the RELAP5 results and on the nodalization qualification process has been examined. The 'steady state' qualification level includes checking the correctness of the initial and boundary conditions and geometrical fidelity. In the 'transient' qualification level, the time dependent results of the code calculation are compared with the experimental time trends from both the qualitative and quantitative point of view. For quantitative assessment of the results, a Fast Fourier Transform Based Method (FFTBM) has been used. The FFTBM was used to establish a range in which the steam generators nodalizations can vary.

  20. Demonstration of the iodine and NO/sub x/ removal systems in the Oak Ridge National Laboratory integrated equipment test facility

    International Nuclear Information System (INIS)

    Lewis, B.E.; Jubin, R.T.

    1987-03-01

    This report summarizes the findings from three sets of experiments on iodine and NO/sub x/ removal performance using dual downdraft condensers in the dissolver off-gas line. The initial experiments were conducted in the laboratory using glassware in proof-of-principle tests. Two additional sets of condenser experiments were conducted using equipment prototyical for a 0.5-t/d plant in the Integrated Equipment Test (IET) facility at the Oak Ridge National Laboratory. This report also describes the NO/sub x/ removal performance of a packed scrubber in the IET during the dissolution of depleted uranium oxides. The overall iodine pass-through efficiency of the condensers in the IET was high as desired. Removal efficiencies ranged from only 0.35 to 6.29%, indicating that the bulk of the iodine in the off-gas will be transferred on through the condensers to the iodox process for final disposal rather than recycled to the dissolver. The optimum operating temperature for the first condenser was in the range of 50 to 70 0 C, with the temperature of the second condenser held near 20 0 C. The NO/sub x/ removal performance of the combined dual condensers and packed scrubber resulted in effluent off-gas stream NO/sub x/ compositions of ∼0.4 to 1.0%, which are acceptable levels for the iodox process. The NO/sub x/ removal efficiency of the condensers ranged from ∼5 to 58%, but was generally around 20%. The removal efficiency of the packed tower scrubber was observed to be in the range of 40 to 60%. The NO/sub x/ removal performance of the condensers tended to complement the performance of the scrubber in that the condenser removal afficiency was high when the scrubber efficiency was low and vice versa

  1. Developing an integrated design model incorporating technology philosophy for the design of healthcare environments : a case analysis of facilities for psychogeriatric and psychiatric care in The Netherlands

    NARCIS (Netherlands)

    van Hoof, J.; Verkerk, M.J.

    The design of healthcare facilities is a complex and dynamic process, which involves many stakeholders each with their own set of needs. In the context of healthcare facilities, this complexity exists at the intersection of technology and society because the very design of these buildings forces us

  2. Wind Energy Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Laurie, Carol

    2017-02-01

    This book takes readers inside the places where daily discoveries shape the next generation of wind power systems. Energy Department laboratory facilities span the United States and offer wind research capabilities to meet industry needs. The facilities described in this book make it possible for industry players to increase reliability, improve efficiency, and reduce the cost of wind energy -- one discovery at a time. Whether you require blade testing or resource characterization, grid integration or high-performance computing, Department of Energy laboratory facilities offer a variety of capabilities to meet your wind research needs.

  3. Waste Facilities

    Data.gov (United States)

    Vermont Center for Geographic Information — This dataset was developed from the Vermont DEC's list of certified solid waste facilities. It includes facility name, contact information, and the materials...

  4. Health Facilities

    Science.gov (United States)

    Health facilities are places that provide health care. They include hospitals, clinics, outpatient care centers, and specialized care centers, ... psychiatric care centers. When you choose a health facility, you might want to consider How close it ...

  5. Fabrication Facilities

    Data.gov (United States)

    Federal Laboratory Consortium — The Fabrication Facilities are a direct result of years of testing support. Through years of experience, the three fabrication facilities (Fort Hood, Fort Lewis, and...

  6. Study protocol for the SMART2D adaptive implementation trial: a cluster randomised trial comparing facility-only care with integrated facility and community care to improve type 2 diabetes outcomes in Uganda, South Africa and Sweden.

    Science.gov (United States)

    Guwatudde, David; Absetz, Pilvikki; Delobelle, Peter; Östenson, Claes-Göran; Olmen Van, Josefien; Alvesson, Helle Molsted; Mayega, Roy William; Ekirapa Kiracho, Elizabeth; Kiguli, Juliet; Sundberg, Carl Johan; Sanders, David; Tomson, Göran; Puoane, Thandi; Peterson, Stefan; Daivadanam, Meena

    2018-03-17

    Type 2 diabetes (T2D) is increasingly contributing to the global burden of disease. Health systems in most parts of the world are struggling to diagnose and manage T2D, especially in low-income and middle-income countries, and among disadvantaged populations in high-income countries. The aim of this study is to determine the added benefit of community interventions onto health facility interventions, towards glycaemic control among persons with diabetes, and towards reduction in plasma glucose among persons with prediabetes. An adaptive implementation cluster randomised trial is being implemented in two rural districts in Uganda with three clusters per study arm, in an urban township in South Africa with one cluster per study arm, and in socially disadvantaged suburbs in Stockholm, Sweden with one cluster per study arm. Clusters are communities within the catchment areas of participating primary healthcare facilities. There are two study arms comprising a facility plus community interventions arm and a facility-only interventions arm. Uganda has a third arm comprising usual care. Intervention strategies focus on organisation of care, linkage between health facility and the community, and strengthening patient role in self-management, community mobilisation and a supportive environment. Among T2D participants, the primary outcome is controlled plasma glucose; whereas among prediabetes participants the primary outcome is reduction in plasma glucose. The study has received approval in Uganda from the Higher Degrees, Research and Ethics Committee of Makerere University School of Public Health and from the Uganda National Council for Science and Technology; in South Africa from the Biomedical Science Research Ethics Committee of the University of the Western Cape; and in Sweden from the Regional Ethical Board in Stockholm. Findings will be disseminated through peer-reviewed publications and scientific meetings. ISRCTN11913581; Pre-results. © Article author(s) (or their

  7. Toroid magnet test facility

    CERN Multimedia

    2002-01-01

    Because of its exceptional size, it was not feasible to assemble and test the Barrel Toroid - made of eight coils - as an integrated toroid on the surface, prior to its final installation underground in LHC interaction point 1. It was therefore decided to test these eight coils individually in a dedicated test facility.

  8. Animal facilities

    International Nuclear Information System (INIS)

    Fritz, T.E.; Angerman, J.M.; Keenan, W.G.; Linsley, J.G.; Poole, C.M.; Sallese, A.; Simkins, R.C.; Tolle, D.

    1981-01-01

    The animal facilities in the Division are described. They consist of kennels, animal rooms, service areas, and technical areas (examining rooms, operating rooms, pathology labs, x-ray rooms, and 60 Co exposure facilities). The computer support facility is also described. The advent of the Conversational Monitor System at Argonne has launched a new effort to set up conversational computing and graphics software for users. The existing LS-11 data acquisition systems have been further enhanced and expanded. The divisional radiation facilities include a number of gamma, neutron, and x-ray radiation sources with accompanying areas for related equipment. There are five 60 Co irradiation facilities; a research reactor, Janus, is a source for fission-spectrum neutrons; two other neutron sources in the Chicago area are also available to the staff for cell biology studies. The electron microscope facilities are also described

  9. Development of Reference Data Set (RDS) for LOBI-MOD2 Integral Test Facility- IAEA Fellowship Training at Nuclear Research Group of San Piero A Grado (GRNSPG), University of PISA, Italy

    International Nuclear Information System (INIS)

    Mohd Rizal Mamat

    2013-01-01

    Deterministic Safety Analysis (DSA) is one of the mandatory requirements conducted for Nuclear Power Plant licensing process in order to ensure compliance with relevant regulatory acceptance criteria. DSA is a technique whereby a set of conservative deterministic rules and requirements are applied for the design and operation of facilities or activities. Computer codes are normally used to assist in performing all required analysis under DSA. In order to ensure a comprehensive analysis, the conduct of DSA should follow a systematic approach. One of the methodologies proposed is the Standardised and Consolidated Reference Experimental (and Calculated) Database (SCRED) developed by University of Pisa which describes the whole processes or steps involved in the preparation of complete database for system thermal-hydraulic code applications for facilities or plants. Under this methodology, the use of Reference Data Set (RDS) as a pre-requisite reference document for developing input nodalization for system thermal-hydraulics code simulation has been proposed. This paper describes the experience of having undergone 2 months of IAEA Fellowship training at Nuclear Research Group of San Piero A Grado (GRNSPG) in University of PISA, Italy and the application of RDS and its effectiveness. Two RDS documents have been developed for an Integral Test Facility of LOBI-MOD2 facility and Test A1-83, 10% small cold leg break LOCA (Loss of Coolant Accident). (author)

  10. HNF - Helmholtz Nano Facility

    Directory of Open Access Journals (Sweden)

    Wolfgang Albrecht

    2017-05-01

    Full Text Available The Helmholtz Nano Facility (HNF is a state-of-the-art cleanroom facility. The cleanroom has ~1100 m2 with cleanroom classes of DIN ISO 1-3. HNF operates according to VDI DIN 2083, Good Manufacturing Practice (GMP and aquivalent to Semiconductor Industry Association (SIA standards. HNF is a user facility of Forschungszentrum Jülich and comprises a network of facilities, processes and systems for research, production and characterization of micro- and nanostructures. HNF meets the basic supply of micro- and nanostructures for nanoelectronics, fluidics. micromechanics, biology, neutron and energy science, etc.. The task of HNF is rapid progress in nanostructures and their technology, offering efficient access to infrastructure and equipment. HNF gives access to expertise and provides resources in production, synthesis, characterization and integration of structures, devices and circuits. HNF covers the range from basic research to application oriented research facilitating a broad variety of different materials and different sample sizes.

  11. Study of the impacts of regulations affecting the acceptance of Integrated Community Energy Systems: public utility, energy facility siting and municipal franchising regulatory programs in the United States. Preliminary background report

    Energy Technology Data Exchange (ETDEWEB)

    Feurer, D.A.; Weaver, C.L.; Gallagher, K.C.; Hejna, D.; Rielley, K.J.

    1980-01-01

    This report is one of a series of preliminary reports describing the laws and regulatory programs of the United States and each of the 50 states affecting the siting and operation of energy generating facilities likely to be used in Integrated Community Energy Systems (ICES). Public utility regulatory statutes, energy facility siting programs, and municipal franchising authority are examined to identify how they may impact on the ability of an organization, whether or not it be a regulated utility, to construct and operate an ICES. This report describes laws and regulatory programs in the United States. Subsequent reports will (1) describe public utility rate regulatory procedures and practices as they might affect an ICES, (2) analyze each of the aforementioned regulatory programs to identify impediments to the development of ICES, and (3) recommend potential changes in legislation and regulatory practices and procedures to overcome such impediments.

  12. VISA-2 - a general, vulnerability-oriented method for evaluating the performance of integrated safeguards/security systems at nuclear facilities

    International Nuclear Information System (INIS)

    Harris, L.; Owel, W.R.

    1981-01-01

    This paper discusses the VISA (Vulnerability of Integrated Safeguards Analysis) method, developed in 1976-77 for the Nuclear Regulatory Commission, and which has been adapted more recently to a broader range of uses. The performance of VISA systems is evaluated in terms of how they perform as an integrated safeguards/security system. The resulting method has been designated VISA-2. 7 refs

  13. Integrating NEPA (National Environmental Policy Act) and CERCLA (Comprehensive Environmental Response, Compensation, and Liability Act) requirements during remedial responses at DOE facilities

    Energy Technology Data Exchange (ETDEWEB)

    Levine, M.B.; Smith, E.D.; Sharples, F.E.; Eddlemon, G.K.

    1990-07-01

    US Department of Energy (DOE) Order 5400.4, issued October 6, 1989, calls for integrating the requirements of the National Environmental Policy Act (NEPA) with those of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) for DOE remedial actions under CERCLA. CERCLA requires that decisions on site remediation be made through a formal process called a Remedial Investigation/Feasibility Study (RI/FS). According to the DOE order, integration is to be accomplished by conducting the NEPA and CERCLA environmental planning and review procedures concurrently. The primary instrument for integrating the processes is to be the RI/FS process, which will be supplemented as needed to meet the procedural and documentational requirements of NEPA. The final product of the integrated process will be a single, integrated set of documents; namely, an RI report and an FS-EIS that satisfy the requirements of both NEPA and CERCLA. The contents of the report include (1) an overview and comparison of the requirements of the two processes; (2) descriptions of the major tasks included in the integrated RI/FS-EIS process; (3) recommended contents for integrated RI/FS-EIS documents; and (4)a discussion of some potential problems in integrating NEPA and CERCLA that fall outisde the scope of the RI/FS-EIS process, with suggestions for resolving some of these problems. 15 refs.

  14. Integrating NEPA [National Environmental Policy Act] and CERCLA [Comprehensive Environmental Response, Compensation, and Liability Act] requirements during remedial responses at DOE facilities

    International Nuclear Information System (INIS)

    Levine, M.B.; Smith, E.D.; Sharples, F.E.; Eddlemon, G.K.

    1990-07-01

    US Department of Energy (DOE) Order 5400.4, issued October 6, 1989, calls for integrating the requirements of the National Environmental Policy Act (NEPA) with those of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) for DOE remedial actions under CERCLA. CERCLA requires that decisions on site remediation be made through a formal process called a Remedial Investigation/Feasibility Study (RI/FS). According to the DOE order, integration is to be accomplished by conducting the NEPA and CERCLA environmental planning and review procedures concurrently. The primary instrument for integrating the processes is to be the RI/FS process, which will be supplemented as needed to meet the procedural and documentational requirements of NEPA. The final product of the integrated process will be a single, integrated set of documents; namely, an RI report and an FS-EIS that satisfy the requirements of both NEPA and CERCLA. The contents of the report include (1) an overview and comparison of the requirements of the two processes; (2) descriptions of the major tasks included in the integrated RI/FS-EIS process; (3) recommended contents for integrated RI/FS-EIS documents; and (4)a discussion of some potential problems in integrating NEPA and CERCLA that fall outisde the scope of the RI/FS-EIS process, with suggestions for resolving some of these problems. 15 refs

  15. Integral test of JENDL-3.2 data by re-analysis of sample reactivity measurements at SEG and STEK facilities

    International Nuclear Information System (INIS)

    Dietze, Klaus

    2001-01-01

    Sample reactivity measurements, which have been performed at the fast-thermal coupled facilities RRR/SEG and STEK, have been re-analyzed using the JNC route for reactor calculation JENDL-3.2 // SLAROM / CITATION / PERKY. C/E-values of central reactivity worths (CRW) of FP nuclides, structural materials, and standards are given. (author)

  16. Facilities Programming.

    Science.gov (United States)

    Bullis, Robert V.

    1992-01-01

    A procedure for physical facilities management written 17 years ago is still worth following today. Each of the steps outlined for planning, organizing, directing, controlling, and evaluating must be accomplished if school facilities are to be properly planned and constructed. However, lessons have been learned about energy consumption and proper…

  17. Nuclear facilities

    International Nuclear Information System (INIS)

    Anon.

    2000-01-01

    Here is given the decree (2000-1065) of the 25. of October 2000 reporting the publication of the convention between the Government of the French Republic and the CERN concerning the safety of the LHC (Large Hadron Collider) and the SPS (Proton Supersynchrotron) facilities, signed in Geneva on July 11, 2000. By this convention, the CERN undertakes to ensure the safety of the LHC and SPS facilities and those of the operations of the LEP decommissioning. The French legislation and regulations on basic nuclear facilities (concerning more particularly the protection against ionizing radiations, the protection of the environment and the safety of facilities) and those which could be decided later on apply to the LHC, SPS and auxiliary facilities. (O.M.)

  18. Estimating the cost of referral and willingness to pay for referral to higher-level health facilities: a case series study from an integrated community case management programme in Uganda.

    Science.gov (United States)

    Nanyonjo, Agnes; Bagorogoza, Benson; Kasteng, Frida; Ayebale, Godfrey; Makumbi, Fredrick; Tomson, Göran; Källander, Karin

    2015-08-28

    Integrated community case management (iCCM) relies on community health workers (CHWs) managing children with malaria, pneumonia, diarrhoea, and referring children when management is not possible. This study sought to establish the cost per sick child referred to seek care from a higher-level health facility by a CHW and to estimate caregivers' willingness to pay (WTP) for referral. Caregivers of 203 randomly selected children referred to higher-level health facilities by CHWs were interviewed in four Midwestern Uganda districts. Questionnaires and document reviews were used to capture direct, indirect and opportunity costs incurred by caregivers, CHWs and health facilities managing referred children. WTP for referral was assessed through the 'bidding game' approach followed by an open-ended question on maximum WTP. Descriptive analysis was conducted for factors associated with referral completion and WTP using logistic and linear regression methods, respectively. The cost per case referred to higher-level health facilities was computed from a societal perspective. Reasons for referral included having fever with a negative malaria test (46.8%), danger signs (29.6%) and drug shortage (37.4%). Among the referred, less than half completed referral (45.8%). Referral completion was 2.8 times higher among children with danger signs (p = 0.004) relative to those without danger signs, and 0.27 times lower among children who received pre-referral treatment (p average cost per case referred was US$ 4.89 and US$7.35 per case completing referral. For each unit cost per case referred, caregiver out of pocket expenditure contributed 33.7%, caregivers' and CHWs' opportunity costs contributed 29.2% and 5.1% respectively and health facility costs contributed 39.6%. The mean (SD) out of pocket expenditure was US$1.65 (3.25). The mean WTP for referral was US$8.25 (14.70) and was positively associated with having received pre-referral treatment, completing referral and increasing

  19. Hydrogen Infrastructure Testing and Research Facility Video (Text Version)

    Science.gov (United States)

    grid integration, continuous code improvement, fuel cell vehicle operation, and renewable hydrogen Systems Integration Facility or ESIF. Research projects including H2FIRST, component testing, hydrogen

  20. The CUTLASS database facilities

    International Nuclear Information System (INIS)

    Jervis, P.; Rutter, P.

    1988-09-01

    The enhancement of the CUTLASS database management system to provide improved facilities for data handling is seen as a prerequisite to its effective use for future power station data processing and control applications. This particularly applies to the larger projects such as AGR data processing system refurbishments, and the data processing systems required for the new Coal Fired Reference Design stations. In anticipation of the need for improved data handling facilities in CUTLASS, the CEGB established a User Sub-Group in the early 1980's to define the database facilities required by users. Following the endorsement of the resulting specification and a detailed design study, the database facilities have been implemented as an integral part of the CUTLASS system. This paper provides an introduction to the range of CUTLASS Database facilities, and emphasises the role of Database as the central facility around which future Kit 1 and (particularly) Kit 6 CUTLASS based data processing and control systems will be designed and implemented. (author)

  1. Mammography Facilities

    Data.gov (United States)

    U.S. Department of Health & Human Services — The Mammography Facility Database is updated periodically based on information received from the four FDA-approved accreditation bodies: the American College of...

  2. Canyon Facilities

    Data.gov (United States)

    Federal Laboratory Consortium — B Plant, T Plant, U Plant, PUREX, and REDOX (see their links) are the five facilities at Hanford where the original objective was plutonium removal from the uranium...

  3. SIGMA Experimental Facility

    International Nuclear Information System (INIS)

    Rivarola, Martin; Florido, Pablo; Gonzalez, Jose; Brasnarof, Daniel; Orellano, Pablo; Bergallo, Juan

    2000-01-01

    The SIGMA ( Separacion Isotopica Gaseosa por Metodos Avanzados) concept is outlined.The old gaseous diffusion process to enrich uranium has been updated to be economically competitive for small production volumes.Major innovations have been introduced in the membrane design and in the integrated design of compressors and diffusers.The use of injectors and gas turbines has been also adopted.The paper describes the demonstration facility installed by the Argentine Atomic Energy Commission

  4. [Integration of new psychosocial facilities into the health care system: considerations on a social ecological evaluation concept exemplified by ambulatory crisis care].

    Science.gov (United States)

    Leferink, K; Bergold, J B

    1996-11-01

    With respect to the methodological problems concerning the outcome evaluation of crisis intervention centers the outlines of a social-ecological research approach are developed. It is suggested that this approach is more suitable to take into account the role of the network of mental health services. The data come from a research project which was designed to explain the historical and social aspects of the process of integration of a crisis intervention service. The results indicate that on the one hand the practice of the service strongly depends on what other services do and on the other hand influences them. The social integration of an institution into the network of other services is discussed as an alternative criterion of evaluation.

  5. Post test calculation of the experiment `small break loss-of- coolant test` SBL-22 at the Finnish integral test facility PACTEL with the thermohydraulic code ATHLET

    Energy Technology Data Exchange (ETDEWEB)

    Lischke, W.; Vandreier, B. [Univ. for Applied Sciences, Zittau/Goerlitz (Germany). Dept. of Nuclear Technology

    1997-12-31

    At the University for Applied Sciences Zittau/Goerlitz (FH) calculations for the verification of the ATHLET-code for reactors of type VVER are carried out since 1991, sponsored by the German Ministry for Education, Science and Technology (BMBF). The special features of these reactors in comparison to reactors of western countries are characterized by the duct route of reactor coolant pipes and the horizontal steam generators. Because of these special features, a check of validity of the ATHLET-models is necessary. For further verification of the ATHLET-code the post test calculation of the experiment SBL-22 (Small break loss-of-coolant test) realized at the finnish facility PACTEL was carried out. The experiment served for the examination of the natural circulation behaviour of the loop over a continuous range of primary side water inventory. 5 refs.

  6. Post test calculation of the experiment 'small break loss-of- coolant test' SBL-22 at the Finnish integral test facility PACTEL with the thermohydraulic code ATHLET

    International Nuclear Information System (INIS)

    Lischke, W.; Vandreier, B.

    1997-01-01

    At the University for Applied Sciences Zittau/Goerlitz (FH) calculations for the verification of the ATHLET-code for reactors of type VVER are carried out since 1991, sponsored by the German Ministry for Education, Science and Technology (BMBF). The special features of these reactors in comparison to reactors of western countries are characterized by the duct route of reactor coolant pipes and the horizontal steam generators. Because of these special features, a check of validity of the ATHLET-models is necessary. For further verification of the ATHLET-code the post test calculation of the experiment SBL-22 (Small break loss-of-coolant test) realized at the finnish facility PACTEL was carried out. The experiment served for the examination of the natural circulation behaviour of the loop over a continuous range of primary side water inventory

  7. Post test calculation of the experiment `small break loss-of- coolant test` SBL-22 at the Finnish integral test facility PACTEL with the thermohydraulic code ATHLET

    Energy Technology Data Exchange (ETDEWEB)

    Lischke, W; Vandreier, B [Univ. for Applied Sciences, Zittau/Goerlitz (Germany). Dept. of Nuclear Technology

    1998-12-31

    At the University for Applied Sciences Zittau/Goerlitz (FH) calculations for the verification of the ATHLET-code for reactors of type VVER are carried out since 1991, sponsored by the German Ministry for Education, Science and Technology (BMBF). The special features of these reactors in comparison to reactors of western countries are characterized by the duct route of reactor coolant pipes and the horizontal steam generators. Because of these special features, a check of validity of the ATHLET-models is necessary. For further verification of the ATHLET-code the post test calculation of the experiment SBL-22 (Small break loss-of-coolant test) realized at the finnish facility PACTEL was carried out. The experiment served for the examination of the natural circulation behaviour of the loop over a continuous range of primary side water inventory. 5 refs.

  8. Design of the PRIDE Facility

    International Nuclear Information System (INIS)

    You, Gil Sung; Choung, Won Myung; Lee, Eun Pyo; Cho, Il Je; Kwon, Kie Chan; Hong, Dong Hee; Lee, Won Kyung; Ku, Jeong Hoe

    2009-01-01

    From 2007, KAERI is developing a PyRoprocess Integrated inactive DEmonstration facility (the PRIDE facility). The maximum annual treatment capacity of this facility will be a 10 ton-HM. The process will use a natural uranium feed material or a natural uranium mixed with some surrogate material for a simulation of a spent fuel. KAERI has also another plan to construct a demonstration facility which can treat a real spent fuel by pyroprocessing. This facility is called by ESPF, Engineering Scale Pyroprocess Facility. The ESPF will have the same treatment capability of spent fuel with the PRIDE facility. The only difference between the PRIDE and the ESPF is a radiation shielding capability. From the PRIDE facility designing works and demonstration with a simulated spent fuel after construction, it will be able to obtain the basic facility requirements, remote operability, interrelation properties between process equipment for designing of the ESPF. The flow sheet of the PRIDE processes is composed of five main processes, such as a decladding and voloxidation, an electro-reduction, an electrorefining, an electro-winning, and a salt waste treatment. The final products from the PRIDE facility are a simulated TRU metal and U metal ingot

  9. A study on the Methodology for Integrated Safety Assessment for Accidental Analysis on LILW managed in Temporary Storage Facility (TSF) at NPP

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, Min Ho; Lee, Kun Jai [Korea Advanced Institute of Science and Technology, 335 Gwahak-ro, yuseong-gu, Daejeon 305-701 (Korea, Republic of); Choi, Kyung Woo [Korea Institute of Nuclear Safety, 34 Gwahak-ro, yuseong-gu, Daejeon 305-338 (Korea, Republic of)

    2010-07-01

    In Korea, the low and intermediate level wastes (LILW) generated from the operation of NPPs have been gradually increased since 1978 because of the absence of the repository for the disposal of LILW. And then, the LILW has being stored in the temporary storage facility (TSF) at each reactor sites. Fortunately, in 2005, the Gyeongju city was selected by the resident's vote in four competitive provinces for the LILW disposal facility. The repository for the disposal of LILW will be operated in end of 2009. In opposition to many of researches on the disposal of LILW, however, the risk assessment on the TSF has scarcely been conducted. Furthermore, the details in regards of the safety analysis on this facility have not been considered in the preliminary and final safety analysis report because this report focused on the nuclear reactor system rather than this facility. As a consequence of these situations, the number of the researches on the arbitrary accidents occurring in the TSF has not been enough. The objective of this study is to establish arbitrary accident scenarios and to evaluate the exposure dose in terms of the effective dose and the thyroid equivalent dose due to the arbitrary accidents originating in the TSF for LILW management. For the establishment of arbitrary accident scenarios in the TSF for LILW, the initiating event was derived by master logic diagram (MLD) method based on the fault tree analysis (FTA), and then arbitrary accident scenarios were developed by the event tree analysis (ETA) through the derived initiating events. The main initiating events led to the arbitrary operational accident, which is the dropping of a drum and fire, were derived from MLD method. The exposure effects resulted from release of radioactive materials related to arbitrary accidents in the TSF for LILW can be divided with the internal exposure caused by breathing and external exposure by radioactive plume. The 13 radionuclides for internal and external exposure

  10. Iodine and NOx behavior in the dissolver off-gas and IODOX [Iodine Oxidation] systems in the Oak Ridge National Laboratory Integrated Equipment Test facility

    International Nuclear Information System (INIS)

    Birdwell, J.F.

    1990-01-01

    This paper describes the most recent in a series of experiments evaluating the behavior of iodine and NO x in the Integrated Equipment Test (IET) Dissolver Off-Gas (DOG) System. This work was performed as part of a joint collaborative program between the US Department of Energy and the Power and Nuclear Fuel Development Corporation of Japan. The DOG system consists of two shell-and-tube heat exchangers in which water and nitric acid are removed from the dissolver off-gas by condensation, followed by a packed tower in which NO x is removed by absorption into a dilute nitric acid solution. The paper also describes the results of the operation of the Iodine Oxidation (IODOX) System. This system serves to remove iodine from the DOG system effluent by absorption into hyperazeotropic nitric acid. 7 refs., 11 figs., 10 tabs

  11. Support facilities

    International Nuclear Information System (INIS)

    Williamson, F.S.; Blomquist, J.A.; Fox, C.A.

    1977-01-01

    Computer support is centered on the Remote Access Data Station (RADS), which is equipped with a 1000 lpm printer, 1000 cpm reader, and a 300 cps paper tape reader with 500-foot spools. The RADS is located in a data preparation room with four 029 key punches (two of which interpret), a storage vault for archival magnetic tapes, card files, and a 30 cps interactive terminal principally used for job inquiry and routing. An adjacent room provides work space for users, with a documentation library and a consultant's office, plus file storage for programs and their documentations. The facility has approximately 2,600 square feet of working laboratory space, and includes two fully equipped photographic darkrooms, sectioning and autoradiographic facilities, six microscope cubicles, and five transmission electron microscopes and one Cambridge scanning electron microscope equipped with an x-ray energy dispersive analytical system. Ancillary specimen preparative equipment includes vacuum evaporators, freeze-drying and freeze-etching equipment, ultramicrotomes, and assorted photographic and light microscopic equipment. The extensive physical plant of the animal facilities includes provisions for holding all species of laboratory animals under controlled conditions of temperature, humidity, and lighting. More than forty rooms are available for studies of the smaller species. These have a potential capacity of more than 75,000 mice, or smaller numbers of larger species and those requiring special housing arrangements. There are also six dog kennels to accommodate approximately 750 dogs housed in runs that consist of heated indoor compartments and outdoor exercise areas

  12. Energy Systems Integration News - October 2016 | Energy Systems Integration

    Science.gov (United States)

    Facility | NREL October 2016 Energy Systems Integration News A monthly recap of the latest energy systems integration (ESI) developments at NREL and around the world. Subscribe Archives October Integration Facility's main control room. OMNETRIC Group Demonstrates a Distributed Control Hierarchy for

  13. Exercise evaluation and simulation facility

    International Nuclear Information System (INIS)

    Meitzler, W.D.; Jaske, R.T.

    1983-12-01

    The Exercise Evaluation and Simulation Facility (EESF) is a mini computer based system that will serve as a tool to aid FEMA in the evaluation of radiological emergency plans and preparedness around commercial nucler power facilities. The EESF integrates the following resources: a meteorological model, dose model, evacuation model, map information, and exercise information into a single system. Thus the user may access these various resources concurrently, and on completion display the results on a color graphic display or hardcopy unit. A unique capability made possible by the integration of these models is the computation of estimated total dose to the population

  14. Use of human factors in the integration of a safety parameter display system (SPDS) and emergency response facility (ERF) capabilities for the James A. Fitzpatrick nuclear power plant

    International Nuclear Information System (INIS)

    Fish, H.C. Jr.; Gutierrez, R.

    1987-01-01

    In 1987, New York Power Authority's Emergency and Process Information Computer (EPIC) System will be operational. The EPIC system was designed to perform two distinct functions: to serve as an advanced replacement for the existing plant process computer and to assist in providing the JAFNPP operations staff with information during plant emergency conditions. Besides meeting the operational and regulatory goals of NYPA, EPIC was designed to meet NYPA human factors criteria. Using human factors literature, industry standards and guidelines, a Human Factors Criteria document was prepared for the EPIC project. This document served as the bases for all hardware, display, and documentation design applicable to EPIC. The major tasks of the EPIC human factors plan include integration of past and present applicable human factors information, establishment of a user definition using data gathered from control room observations (startup and shutdown of JAFNPP), survey of computer programs used by the operators, and obtaining input from licensed operators. These major tasks played a role in the design of the design of the control room configuration, the design and development of computer generated displays, and the format in which the displayed and hard copy information would be presented to the user. This paper presents an overview of the human factors work performed and the documents researched or developed in the design of EPIC displays, software, and hardware. The location and operation of this new computer based information system, like the displays was based on the systematic application of operations and human factors principles

  15. Facilities evaluation report

    International Nuclear Information System (INIS)

    Sloan, P.A.; Edinborough, C.R.

    1992-04-01

    The Buried Waste Integrated Demonstration (BWID) is a program of the Department of Energy (DOE) Office of Technology Development whose mission is to evaluate different new and existing technologies and determine how well they address DOE community waste remediation problems. Twenty-three Technical Task Plans (TTPs) have been identified to support this mission during FY-92; 10 of these have identified some support requirements when demonstrations take place. Section 1 of this report describes the tasks supported by BWID, determines if a technical demonstration is proposed, and if so, identifies the support requirements requested by the TTP Principal Investigators. Section 2 of this report is an evaluation identifying facility characteristics of existing Idaho National Engineering Laboratory (INEL) facilities that may be considered for use in BWID technology demonstration activities

  16. Integrated management of organic wastes for remediation of massive tailings storage facilities under semiarid mediterranean climate type: efficacy of organic pork residues as study case

    Science.gov (United States)

    Ginocchio, Rosanna; Arellano, Eduardo; España, Helena; Gardeweg, Rosario; Bas, Fernando; Gandarillas, Mónica

    2016-04-01

    Remediation of large surface areas of massive mine wastes, such as tailings storage facilities (TSFs) is challenging, particularly when no topsoils have been stored for the mine closure stage. Worldwide, it has been demonstrated that the use of organic wastes as substrate amendments for remediation of hard rock mine wastes is a useful alternative to topsoils material. In the case of semi-arid climate conditions of north-central Chile, the copper mining industry has generated massive TSF (between 400 ha and 3,000 ha) which needs now to be properly closed according to recently established mine closure regulations. However, in most of the cases, there have been no topsoils savage that facilitate the initial stage of the site remediation. Industrial organic wastes (i.e. biosolids) are found in the area, but their availability is normally below the demand needed for remediation of TSFs and salt content is normally elevated, thus posing salinization risks to the substrate and negative plant growth. We focused on a large organic waste producing industry, the pork industry, whose growth has been restricted due to the limited possibilities for using pig slurries as amendments for croplands in north-central Chile and the strong odor generated, resulting in conflicts with local communities. Incorporation of pig slurries as amendments to post-operative TSFs has been scarcely evaluated at international level (i.e. Spain) and no evaluation at all exists for the solid organic fraction generated from pig slurry treatment plants (PSTP). In the present study, we evaluated the efficacy of both pig slurries (PS) and the solid fraction of PSTP (SF-PSTP) as tailings amendment for creating good plant productivity on TSFs located under semi-arid Mediterranean climate conditions in north-central Chile. A short-term greenhouse study was developed. Copper mine tailings were mixed either with PS (0, 40, 80, and 120 m3 ha-1) or SF-PSTP (0, 25, 50 and 75 t ha-1), distributed in 3 L pots, and

  17. Demonstration of the iodine and NO/sub x/ removal systems in the Oak Ridge National Laboratory (ORNL) Integrated Equipment Test (IET) facility

    International Nuclear Information System (INIS)

    Jubin, R.T.; Lewis, B.E.

    1986-01-01

    The overall iodine removal performance of the condensers during phase-two experiments was good (i.e., very small amounts of iodine were recycled), with removal efficiency for both condensers ranging from 0.35 to 6.29%. The removal efficiency for the first condenser ranged from 0.03 to 5.78%, and the second condenser, from 0.02 to 3.42%. In all the cases studied, the overall iodine removal efficiency appeared to be smallest, with the first condenser operating near 50 0 C. While the 50 0 C operating temperature is not necessarily the optimum temperature, the data appear to indicate that the optimum is bounded by 50 and 70 0 C. Phase three of the Integrated Equipment Test dissolver off-gas (DOG) system tests verified the operation of the dual condensers and the NO/sub x/ scrubber column under a variety of operating conditions. The removal efficiencies of the condensers were higher than anticipated, generally approx.20% in these tests. The scrubber provided an NO/sub x/ effluent of approx.0.4 to 1.0% during the entire campaign, which is consistent with the acceptable NO/sub x/ levels in the off-gas to Iodox. In addition, this 0.4-to-1.0% NO/sub x/ level in the scrubber effluent confirms the BRET design decision to omit the NO/sub x/ scrubber in a system with a DOG NO/sub x/ concentration of approx.1.0%

  18. Emission Facilities - Erosion & Sediment Control Facilities

    Data.gov (United States)

    NSGIC Education | GIS Inventory — An Erosion and Sediment Control Facility is a DEP primary facility type related to the Water Pollution Control program. The following sub-facility types related to...

  19. Performance of Shiva as a laser fusion irradiation facility

    International Nuclear Information System (INIS)

    Speck, D.R.; Bliss, E.S.; Glaze, J.A.; Johnson, B.C.; Manes, K.R.; Ozarski, R.G.; Rupert, P.R.; Simmons, W.W.; Swift, C.D.; Thompson, C.E.

    1979-01-01

    Shiva is a 20 beam Nd:Glass Laser and Target Irradiation Facility at the Lawrence Livermore Laboratory. The laser system and integrated target facility evolved during the last year from a large, untested, experimental laser system to a target irradiation facility which has provided significant laser driven inertial confinement fusion data. The operation of the facility is discussed

  20. The utah beacon experience: integrating quality improvement, health information technology, and practice facilitation to improve diabetes outcomes in small health care facilities.

    Science.gov (United States)

    Tennison, Janet; Rajeev, Deepthi; Woolsey, Sarah; Black, Jeff; Oostema, Steven J; North, Christie

    2014-01-01

    The Utah Improving Care through Connectivity and Collaboration (IC3) Beacon community (2010-2013) was spearheaded by HealthInsight, a nonprofit, community-based organization. One of the main objectives of IC(3) was to improve health care provided to patients with diabetes in three Utah counties, collaborating with 21 independent smaller clinics and two large health care enterprises. This paper will focus on the use of health information technology (HIT) and practice facilitation to develop and implement new care processes to improve clinic workflow and ultimately improve patients' diabetes outcomes at 21 participating smaller, independent clinics. Early in the project, we learned that most of the 21 clinics did not have the resources needed to successfully implement quality improvement (QI) initiatives. IC(3) helped clinics effectively use data generated from their electronic health records (EHRs) to design and implement interventions to improve patients' diabetes outcomes. This close coupling of HIT, expert practice facilitation, and Learning Collaboratives was found to be especially valuable in clinics with limited resources. Through this process we learned that (1) an extensive readiness assessment improved clinic retention, (2) clinic champions were important for a successful collaboration, and (3) current EHR systems have limited functionality to assist in QI initiatives. In general, smaller, independent clinics lack knowledge and experience with QI and have limited HIT experience to improve patient care using electronic clinical data. Additionally, future projects like IC(3) Beacon will be instrumental in changing clinic culture so that QI is integrated into routine workflow. Our efforts led to significant changes in how practice staff optimized their EHRs to manage and improve diabetes care, while establishing the framework for sustainability. Some of the IC(3) Beacon practices are currently smoothly transitioning to new models of care such as Patient

  1. Review of the Tritium Extraction Facility design

    International Nuclear Information System (INIS)

    Barton, R.W.; Bamdad, F.; Blackman, J.

    2000-01-01

    The Defense Nuclear Facilities Safety Board (DNFSB) is an independent executive branch agency responsible for technical safety oversight of the US Department of Energy's (DOE's) defense nuclear facilities. One of DNFSB's responsibilities is the review of design and construction projects for DOE's defense nuclear facilities to ensure that adequate health and safety requirements are identified and implemented. These reviews are performed with the expectation that facility designs are being developed within the framework of a site's Integrated Safety Management (ISM) program. This paper describes the application of ISM principles in DNFSB's ongoing review of the Tritium Extraction Facility (TEF) design/construction project

  2. Review of the Tritium Extraction Facility Design

    International Nuclear Information System (INIS)

    Ronald W. Barton; Farid Bamdad; Joel Blackman

    2000-01-01

    The Defense Nuclear Facilities Safety Board (DNFSB) is an independent executive branch agency responsible for technical safety oversight of the U.S. Department of Energy's (DOE's) defense nuclear facilities. One of DNFSB's responsibilities is the review of design and construction projects for DOE's defense nuclear facilities to ensure that adequate health and safety requirements are identified and implemented. These reviews are performed with the expectation that facility designs are being developed within the framework of a site's Integrated Safety Management (ISM) program. This paper describes the application of ISM principles in DNFSB's ongoing review of the Tritium Extraction Facility (TEF) design/construction project

  3. Facility effluent monitoring plan for the plutonium uranium extraction facility

    Energy Technology Data Exchange (ETDEWEB)

    Wiegand, D.L.

    1994-09-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years.

  4. Facility Effluent Monitoring Plan for the uranium trioxide facility

    International Nuclear Information System (INIS)

    Lohrasbi, J.; Johnson, D.L.; De Lorenzo, D.S.

    1993-12-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years

  5. Facility effluent monitoring plan for the plutonium uranium extraction facility

    International Nuclear Information System (INIS)

    Wiegand, D.L.

    1994-09-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years

  6. Facility effluent monitoring plan for the Plutonium Uranium Extraction Facility

    International Nuclear Information System (INIS)

    Greager, E.M.

    1997-01-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan will ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated, at a minimum, every 3 years

  7. Air Quality Facilities

    Data.gov (United States)

    Iowa State University GIS Support and Research FacilityFacilities with operating permits for Title V of the Federal Clean Air Act, as well as facilities required to submit an air emissions inventory, and other facilities...

  8. Facility model for the Los Alamos Plutonium Facility

    International Nuclear Information System (INIS)

    Coulter, C.A.; Thomas, K.E.; Sohn, C.L.; Yarbro, T.F.; Hench, K.W.

    1986-01-01

    The Los Alamos Plutonium Facility contains more than sixty unit processes and handles a large variety of nuclear materials, including many forms of plutonium-bearing scrap. The management of the Plutonium Facility is supporting the development of a computer model of the facility as a means of effectively integrating the large amount of information required for material control, process planning, and facility development. The model is designed to provide a flexible, easily maintainable facility description that allows the faciltiy to be represented at any desired level of detail within a single modeling framework, and to do this using a model program and data files that can be read and understood by a technically qualified person without modeling experience. These characteristics were achieved by structuring the model so that all facility data is contained in data files, formulating the model in a simulation language that provides a flexible set of data structures and permits a near-English-language syntax, and using a description for unit processes that can represent either a true unit process or a major subsection of the facility. Use of the model is illustrated by applying it to two configurations of a fictitious nuclear material processing line

  9. Large laser system facility design

    International Nuclear Information System (INIS)

    Gilmartin, T.J.

    1983-01-01

    Optical stability of foundations and support structures, environmental control, close-in subsystem integration, spatial organization, materiel flow and access to remote subsystems is discussed and compared for four laser facilities: The Special Isotope Separation Laboratory, Argus, Shiva/Nova, and Firepond

  10. CLAIMS OF SUSTAINABLE FACILITIES MANAGEMENT

    DEFF Research Database (Denmark)

    Nielsen, Susanne Balslev

    Purpose: The purpose of the paper is to provide an overview of current practices within the emergent management discipline: Sustainable Facilities Management (SFM). Background: To develop a sustainable society, facilities managers must become change agents for sustainability in the built...... environment. Facilities Management (FM) is contributing to the environmental, social and economical problems, but can at the same time also be a part of the solution. However, to integrate sustainability in FM is still an emergent niche within FM, and the examples of SFM so far seems to come out of very......-creating of new socio-technical services and technologies These SFM understandings are concluded to be coexisting claims of SFM definitions. Practical Implications: Facilities managers will be able to identify the mindset behind different services and technologies that are promoted as SFM. But maybe just...

  11. ATLAS Facility Description Report

    International Nuclear Information System (INIS)

    Kang, Kyoung Ho; Moon, Sang Ki; Park, Hyun Sik; Cho, Seok; Choi, Ki Yong

    2009-04-01

    A thermal-hydraulic integral effect test facility, ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation), has been constructed at KAERI (Korea Atomic Energy Research Institute). The ATLAS has the same two-loop features as the APR1400 and is designed according to the well-known scaling method suggested by Ishii and Kataoka to simulate the various test scenarios as realistically as possible. It is a half-height and 1/288-volume scaled test facility with respect to the APR1400. The fluid system of the ATLAS consists of a primary system, a secondary system, a safety injection system, a break simulating system, a containment simulating system, and auxiliary systems. The primary system includes a reactor vessel, two hot legs, four cold legs, a pressurizer, four reactor coolant pumps, and two steam generators. The secondary system of the ATLAS is simplified to be of a circulating loop-type. Most of the safety injection features of the APR1400 and the OPR1000 are incorporated into the safety injection system of the ATLAS. In the ATLAS test facility, about 1300 instrumentations are installed to precisely investigate the thermal-hydraulic behavior in simulation of the various test scenarios. This report describes the scaling methodology, the geometric data of the individual component, and the specification and the location of the instrumentations in detail

  12. Mixed Waste Management Facility

    International Nuclear Information System (INIS)

    Brummond, W.; Celeste, J.; Steenhoven, J.

    1993-08-01

    The DOE has developed a National Mixed Waste Strategic Plan which calls for the construction of 2 to 9 mixed waste treatment centers in the Complex in the near future. LLNL is working to establish an integrated mixed waste technology development and demonstration system facility, the Mixed Waste Management Facility (MWMF), to support the DOE National Mixed Waste Strategic Plan. The MWMF will develop, demonstrate, test, and evaluate incinerator-alternatives which will comply with regulations governing the treatment and disposal of organic mixed wastes. LLNL will provide the DOE with engineering data for design and operation of new technologies which can be implemented in their mixed waste treatment centers. MWMF will operate under real production plant conditions and process samples of real LLNL mixed waste. In addition to the destruction of organic mixed wastes, the development and demonstration will include waste feed preparation, material transport systems, aqueous treatment, off-gas treatment, and final forms, thus making it an integrated ''cradle to grave'' demonstration. Technologies from offsite as well as LLNL's will be tested and evaluated when they are ready for a pilot scale demonstration, according to the needs of the DOE

  13. 1999 status of the Aube facility

    International Nuclear Information System (INIS)

    2000-01-01

    This document presents a status of the life of the Aube radioactive waste facility under its different aspects: technical, economical, social and ecological (exploitation indicators, origin of the personnel, local integration etc..). (J.S.)

  14. Enforcement and Compliance History Online (ECHO) Facilities

    Data.gov (United States)

    U.S. Environmental Protection Agency — ECHO provides integrated compliance and enforcement information for about 800,000 regulated facilities nationwide. Its features range from simple to advanced,...

  15. Performance specifications for proton medical facility

    Energy Technology Data Exchange (ETDEWEB)

    Chu, W.T.; Staples, J.W.; Ludewigt, B.A.; Renner, T.R.; Singh, R.P.; Nyman, M.A.; Collier, J.M.; Daftari, I.K.; Petti, P.L.; Alonso, J.R. [Lawrence Berkeley Lab., CA (United States); Kubo, H.; Verhey, L.J. [University of California Davis Medical Center, Sacramento, CA (United States). Cancer Center]|[California Univ., San Francisco, CA (United States). School of Medicine; Castro, J.R. [Lawrence Berkeley Lab., CA (United States)]|[University of California Davis Medical Center, Sacramento, CA (United States). Cancer Center]|[California Univ., San Francisco, CA (United States). School of Medicine

    1993-03-01

    Performance specifications of technical components of a modern proton radiotherapy facility are presented. The technical items specified include: the accelerator; the beam transport system including rotating gantry; the treatment beamline systems including beam scattering, beam scanning, and dosimetric instrumentation; and an integrated treatment and accelerator control system. Also included are treatment ancillary facilities such as diagnostic tools, patient positioning and alignment devices, and treatment planning systems. The facility specified will accommodate beam scanning enabling the three-dimensional conformal therapy deliver .

  16. Agricultural research conducted after Fukushima Nuclear Power Plant accident. An approach integrating all of the departments and facilities in Graduate School of Agricultural and Life Sciences, the University of Tokyo

    International Nuclear Information System (INIS)

    Nakanishi, Tomoko M.

    2012-01-01

    After Fukushima nuclear power plant accident, more than 40 academic staffs at Graduate School of Agricultural and Life Sciences, The Univ. of Tokyo, have been conducted agricultural research integrating all of the departments and facilities. They were divided into several groups, such as grain, animal stock, fishery, trees, wild lives, etc. The agricultural research is highly related to nature itself; therefore, cooperative research gathering several kinds of researchers is needed. For example, to analyze the radioactive accumulation in rice, not only rice breeding researcher but also soil researcher, water management researcher, etc. are needed to discuss the movement or pathway of radioactive nuclides in the field. We found that the fallout was adsorbed at the surface of anything expanded and exposed to the air at the time of the accident, such as soil surface, plant leaves, tree trunks, etc. The adsorption comes stronger with time so that the radioactivity in soil does not move downward any more after several months, in spite of much rain. In the case of plants, the radioactivity still remains as dots on the surface of the tissue and it is very difficult to remove the nuclides even by washing with acids. Mushrooms were found to accumulate high radioactivity, not only the fallout from Fukushima's accident but also the fallout in 1960's after nuclear test bomb. (author)

  17. Reactor facility

    International Nuclear Information System (INIS)

    Suzuki, Hiroaki; Murase, Michio; Yokomizo, Osamu.

    1997-01-01

    The present invention provides a BWR type reactor facility capable of suppressing the amount of steams generated by the mutual effect of a failed reactor core and coolants upon occurrence of an imaginal accident, and not requiring spacial countermeasures for enhancing the pressure resistance of the container vessel. Namely, a means for supplying cooling water at a temperature not lower by 30degC than the saturated temperature corresponding to the inner pressure of the containing vessel upon occurrence of an accident is disposed to a lower dry well below the pressure vessel. As a result, upon occurrence of such an accident that the reactor core should be melted and flown downward of the pressure vessel, when cooling water at a temperature not lower than the saturated temperature, for example, cooling water at 100degC or higher is supplied to the lower dry well, abrupt generation of steams by the mutual effect of the failed reactor core and cooling water is scarcely caused compared with a case of supplying cooling water at a temperature lower than the saturation temperature by 30degC or more. Accordingly, the amount of steams to be generated can be suppressed, and special countermeasure is no more necessary for enhancing the pressure resistance of the container vessel is no more necessary. (I.S.)

  18. Nuclear facilities

    International Nuclear Information System (INIS)

    Anon.

    2002-01-01

    During September and October 2001, 15 events were recorded on the first grade and 1 on the second grade of the INES scale. The second grade event is in fact a re-classification of an incident that occurred on the second april 2001 at Dampierre power plant. This event happened during core refueling, a shift in the operation sequence led to the wrong positioning of 113 assemblies. A preliminary study of this event shows that this wrong positioning could have led, in other circumstances, to the ignition of nuclear reactions. Even in that case, the analysis made by EDF shows that the consequences on the staff would have been limited. Nevertheless a further study has shown that the existing measuring instruments could not have detected the power increase announcing the beginning of the chain reaction. The investigation has shown that there were deficiencies in the control of the successive operations involved in refueling. EDF has proposed a series of corrective measures to be implemented in all nuclear power plants. The other 15 events are described in the article. During this period 121 inspections have been made in nuclear facilities. (A.C.)

  19. Marketing Sports Facilities: Perspectives from Botswana

    Science.gov (United States)

    Bohutsana, Basuti; Akpata, Dele

    2013-01-01

    The provision of sports facilities contributes immensely to the growth of sports and leisure activities in the countries where they are provided. In some countries, as was the case in Botswana, the government had to spend millions of dollars to provide new Integrated Sports Facilities (ISF's) as a panacea for the continued poor performance of its…

  20. Facility management research in the Netherlands

    NARCIS (Netherlands)

    Thijssen, Thomas; van der Voordt, Theo; Mobach, Mark P.

    This article provides a brief overview of the history and development of facility management research in the Netherlands and indicates future directions. Facility management as a profession has developed from single service to multi-services and integral services over the past 15 years.

  1. Institutionalizing Safeguards By Design for Nuclear Facilities

    International Nuclear Information System (INIS)

    Morgan, James B.; Kovacic, Donald N.; Whitaker, J. Michael

    2008-01-01

    Safeguards for nuclear facilities can be significantly improved by developing and implementing methodologies for integrating proliferation resistance into the design of new facilities. This paper proposes a method to systematically analyze a facility's processes, systems, equipment, structures and management controls to ensure that all relevant proliferation scenarios that could potentially result in unacceptable consequences have been identified, evaluated and mitigated. This approach could be institutionalized into a country's regulatory structure similar to the way facilities are licensed to operate safely and are monitored through inspections and incident reporting to ensure compliance with domestic and international safeguards. Furthermore, taking credit for existing systems and equipment that have been analyzed and approved to assure a facility's reliable and safe operations will reduce the overall cost of implementing intrinsic and extrinsic proliferation-resistant features. The ultimate goal is to integrate safety, reliability, security and safeguards operations into the design of new facilities to effectively and efficiently prevent diversion, theft and misuse of nuclear material and sensitive technologies at both the facility and state level. To facilitate this approach at the facility level, this paper discusses an integrated proliferation resistance analysis (IPRA) process. If effectively implemented, this integrated approach will also facilitate the application of International Atomic Energy Agency (IAEA) safeguards

  2. EPA Facility Registry System (FRS): NCES

    Science.gov (United States)

    This web feature service contains location and facility identification information from EPA's Facility Registry System (FRS) for the subset of facilities that link to the National Center for Education Statistics (NCES). The primary federal database for collecting and analyzing data related to education in the United States and other Nations, NCES is located in the U.S. Department of Education, within the Institute of Education Sciences. FRS identifies and geospatially locates facilities, sites or places subject to environmental regulations or of environmental interest. Using vigorous verification and data management procedures, FRS integrates facility data from EPA00e2??s national program systems, other federal agencies, and State and tribal master facility records and provides EPA with a centrally managed, single source of comprehensive and authoritative information on facilities. This data set contains the subset of FRS integrated facilities that link to NCES school facilities once the NCES data has been integrated into the FRS database. Additional information on FRS is available at the EPA website http://www.epa.gov/enviro/html/fii/index.html.

  3. Socio-environmental integration of hydropower facilities

    International Nuclear Information System (INIS)

    Harby, Atle; Forseth, Torbjoern; Ruud, Audun; Bakken, Tor Haakon

    2017-01-01

    Centre for Environmental Design of Renewable Energy (CEDREN) is a research centre focusing on hydropower production and environmental impacts of hydropower. The main objective of CEDREN is to develop and communicate design solutions for renewable energy production that address environmental and societal challenges at local, regional, national and global levels. Environmental design means that planning, building and operation have to include technical, economic, environmental and socio-political aspects throughout the whole life-span of the project. Methods and tools to ensure environmental design are developed in CEDREN and applied to case studies in Norway and internationally. These methods and tools focus on finding physical and biological bottlenecks for affected species and ecosystems by mapping, modelling and analysis of both physical conditions and ecological status. CEDREN proposes different measures, tools and methods to improve the environmental conditions as well as how to maintain or increase the power production. In addition, a strong focus must be made on political governance to ensure more representative participation of relevant stakeholders in the process of finding the best technical, economic and political solutions for power production, the environment and the society. Key research findings used to develop relationships between physical factors like flow, flow fluctuations, water temperature, water velocity, water depth and water-covered area and biological response will be shown. Examples of improved methods for better planning procedures with stakeholder engagement will be proposed. Examples of methods and tools for environmental design of hydropower will be given for several regulated rivers in Norway and abroad. (authors)

  4. Development of an integrated assay facility

    International Nuclear Information System (INIS)

    Molesworth, T.V.; Bailey, M.; Findlay, D.J.S.; Sene, M.R.; Swinhoe, M.T.

    1990-01-01

    Initial results of active neutron and active gamma-ray interrogation of a 500 liter cemented simulated CAGR intermediate level radioactive waste drum are described. The basis of the interrogation systems was the Harwell electron linear accelerator HELIOS, which was used to produce the interrogating neutrons and gamma-rays. Several sets of neutron detectors were located around the drum to count signature neutrons. The responses of the system were measured by placing known samples at many different locations within the drum. In general, measured responses confirmed calculated responses. Good agreement was obtained for the azimuthal angle dependences. The absolute responses agreed well for gamma-ray interrogation, but the calculations were apparently over-estimates for neutron interrogation. Those aspects requiring consideration in the practical application of assay techniques are identified. 8 refs., 6 figs

  5. Publications | Energy Systems Integration Facility | NREL

    Science.gov (United States)

    Photovoltaic Power Plant An Illustration of people in a park with wind turbines and solar panels Achieving a Management System Solar panels on home in Kaupuni Villiage in Oahu, Hawaii Hawaiian Electric Advanced

  6. Facility effluent monitoring plan for 242-A evaporator facility

    International Nuclear Information System (INIS)

    Crummel, G.M.; Gustavson, R.D.

    1995-02-01

    A facility effluent monitoring plan is required by the U.S. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could affect employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation showed the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-1. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated, as a minimum, every three years

  7. Solder bond requirement for large, built-up, high-performance conductors

    International Nuclear Information System (INIS)

    Willig, R.L.

    1981-01-01

    Some large built-up conductors fabricated for large superconducting magnets are designed to operate above the maximum recovery current. Because the stability of these conductors is sensitive to the quality of the solder bond joining the composite superconductor to the high-conductivity substrate, a minimum bond requirement is necessary. The present analysis finds that the superconductor is unstable and becomes abruptly resistive when there are temperature excursions into the current sharing region of a poorly bonded conductor. This abrupt transition, produces eddy current heating in the vicinity of the superconducting filaments and causes a sharp reduction in the minimum propagating zone (MPZ) energy. This sensitivity of the MPZ energy to the solder bond contact area is used to specify a minimum bond requirement. For the superconducting MHD magnet built for the Component Development Integration Facility (CDIF), the minimum bonded surface area is .68 cm/sup 2//cm which is 44% of the composite perimeter. 5 refs

  8. Irradiation Facilities at CERN

    CERN Document Server

    Gkotse, Blerina; Carbonez, Pierre; Danzeca, Salvatore; Fabich, Adrian; Garcia, Alia, Ruben; Glaser, Maurice; Gorine, Georgi; Jaekel, Martin, Richard; Mateu,Suau, Isidre; Pezzullo, Giuseppe; Pozzi, Fabio; Ravotti, Federico; Silari, Marco; Tali, Maris

    2017-01-01

    CERN provides unique irradiation facilities for applications in many scientific fields. This paper summarizes the facilities currently operating for proton, gamma, mixed-field and electron irradiations, including their main usage, characteristics and information about their operation. The new CERN irradiation facilities database is also presented. This includes not only CERN facilities but also irradiation facilities available worldwide.

  9. Research Facilities | Wind | NREL

    Science.gov (United States)

    Research Facilities Research Facilities NREL's state-of-the-art wind research facilities at the Research Facilities Photo of five men in hard hards observing the end of a turbine blade while it's being tested. Structural Research Facilities A photo of two people silhouetted against a computer simulation of

  10. North Slope, Alaska ESI: FACILITY (Facility Points)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This data set contains data for oil field facilities for the North Slope of Alaska. Vector points in this data set represent oil field facility locations. This data...

  11. Facility effluent monitoring plan for the tank farms facilities

    Energy Technology Data Exchange (ETDEWEB)

    Bachand, D.D.; Crummel, G.M.

    1995-05-01

    A facility effluent monitoring plan is required by the US Department of Energy for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using specific guidelines. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years.

  12. Jupiter Laser Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Jupiter Laser Facility is an institutional user facility in the Physical and Life Sciences Directorate at LLNL. The facility is designed to provide a high degree...

  13. Basic Research Firing Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Basic Research Firing Facility is an indoor ballistic test facility that has recently transitioned from a customer-based facility to a dedicated basic research...

  14. Environmental restoration plan for the transfer of surplus facilities to the Facility Transition Program at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    1995-08-01

    This report will provide guidance on management, coordination, and integration of plans to transition facilities to the Facility Transition Program and activities as related to the Oak Ridge National Laboratory (ORNL) Environmental Restoration Program facilities. This report gives (1) guidance on the steps necessary for identifying ORNL surplus facilities, (2) interfaces of Surveillance and Maintenance (S and M) and Isotope Facility Deactivation program managers, (3) roles and responsibilities of the facility managers, and (4) initial S and M requirements upon acceptance into the Facility Transition Program

  15. The National Ignition Facility

    International Nuclear Information System (INIS)

    Hogan, W.J.; Moses, E.; Warner, B.; Sorem, M.; Soures, J.M.

    2001-01-01

    The National Ignition Facility (NIF) is the largest construction project ever undertaken at Lawrence Livermore National Laboratory (LLNL). NIF consists of 192 forty-centimeter-square laser beams and a 10-m-diameter target chamber. NIF is being designed and built by an LLNL-led team from Los Alamos National Laboratory, Sandia National Laboratories, the University of Rochester, and LLNL. Physical construction began in 1997. The Laser and Target Area Building and the Optics Assembly Building were the first major construction activities, and despite several unforeseen obstacles, the buildings are now 92% complete and have been done on time and within cost. Prototype component development and testing has proceeded in parallel. Optics vendors have installed full-scale production lines and have done prototype production runs. The assembly and integration of the beampath infrastructure has been reconsidered and a new approach has been developed. This paper will discuss the status of the NIF project and the plans for completion. (author)

  16. Energy Systems Integration News | Energy Systems Integration Facility |

    Science.gov (United States)

    organization and independent system operator settle energy transactions in its real-time markets at the same time interval it dispatches energy, and settle operating reserves transactions in its real-time markets the electric grid. These control systems will enable real-time coordination between distributed energy

  17. Energy Systems Integration News | Energy Systems Integration Facility |

    Science.gov (United States)

    determine how well a solar photovoltaic (PV) system with battery energy storage can provide backup power to . These analyses will result in a design guide for climate-specific sizing of the system. NREL's Erfan , feasibility, and operational analyses for photovoltaic and concentrating solar power generation projects

  18. Energy Systems Integration News | Energy Systems Integration Facility |

    Science.gov (United States)

    grids. In terms of paper sessions, NREL ESI researcher Santosh Veda chaired a session on energy Kroposki chaired a session on advanced renewable energy power systems. While Veda, Muljadi, and Kroposki

  19. Energy Systems Integration News | Energy Systems Integration Facility |

    Science.gov (United States)

    NREL six people standing at a table with various containers of pet food. NREL's ESI program included with this release. Register for the webinar. Presentations Available from Last Month's High withstand the crucial first minute after severe grid disturbances with high penetrations of wind and solar

  20. Energy Systems Integration News | Energy Systems Integration Facility |

    Science.gov (United States)

    distributed energy resourcessolar panels, wind turbines, microgrids, and battery storagethat use smart ) panels respond to changes in solar conditions. In addition to the design and construction of the new

  1. Energy Systems Integration News | Energy Systems Integration Facility |

    Science.gov (United States)

    NREL January 2018 Blockchain concept demonstrated Blockchain to Enable Energy Market in BlockCypher Partnership NREL is partnering with BlockCypher, a blockchain Web services provider, to demonstrate how blockchain technology can support distributed energy markets. For some, the language and

  2. Tritium Systems Test Facility

    International Nuclear Information System (INIS)

    Cafasso, F.A.; Maroni, V.A.; Smith, W.H.; Wilkes, W.R.; Wittenberg, L.J.

    1978-01-01

    This TSTF proposal has two principal objectives. The first objective is to provide by mid-FY 1981 a demonstration of the fuel cycle and tritium containment systems which could be used in a Tokamak Experimental Power Reactor for operation in the mid-1980's. The second objective is to provide a capability for further optimization of tritium fuel cycle and environmental control systems beyond that which is required for the EPR. The scale and flow rates in TSTF are close to those which have been projected for a prototype experimental power reactor (PEPR/ITR) and will permit reliable extrapolation to the conditions found in an EPR. The fuel concentrations will be the same as in an EPR. Demonstrations of individual components of the deuterium-tritium fuel cycle and of monitoring, accountability and containment systems and of a maintenance methodology will be achieved at various times in the FY 1979-80 time span. Subsequent to the individual component demonstrations--which will proceed from tests with hydrogen (and/or deuterium) through tracer levels of tritium to full operational concentrations--a complete test and demonstration of the integrated fuel processing and tritium containment facility will be performed. This will occur near the middle of FY 1981. Two options were considered for the TSTF: (1) The modification of an existing building and (2) the construction of a new facility

  3. Aperture area measurement facility

    Data.gov (United States)

    Federal Laboratory Consortium — NIST has established an absolute aperture area measurement facility for circular and near-circular apertures use in radiometric instruments. The facility consists of...

  4. High Throughput Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Argonne?s high throughput facility provides highly automated and parallel approaches to material and materials chemistry development. The facility allows scientists...

  5. Licensed Healthcare Facilities

    Data.gov (United States)

    California Natural Resource Agency — The Licensed Healthcare Facilities point layer represents the locations of all healthcare facilities licensed by the State of California, Department of Health...

  6. A Bioinformatics Facility for NASA

    Science.gov (United States)

    Schweighofer, Karl; Pohorille, Andrew

    2006-01-01

    Building on an existing prototype, we have fielded a facility with bioinformatics technologies that will help NASA meet its unique requirements for biological research. This facility consists of a cluster of computers capable of performing computationally intensive tasks, software tools, databases and knowledge management systems. Novel computational technologies for analyzing and integrating new biological data and already existing knowledge have been developed. With continued development and support, the facility will fulfill strategic NASA s bioinformatics needs in astrobiology and space exploration. . As a demonstration of these capabilities, we will present a detailed analysis of how spaceflight factors impact gene expression in the liver and kidney for mice flown aboard shuttle flight STS-108. We have found that many genes involved in signal transduction, cell cycle, and development respond to changes in microgravity, but that most metabolic pathways appear unchanged.

  7. Integral fast reactor concept

    International Nuclear Information System (INIS)

    Chang, Y.I.; Marchaterre, J.F.; Sevy, R.H.

    1984-01-01

    Key features of the IFR consist of a pool-type plant arrangement, a metal fuel-based core design, and an integral fuel cycle with colocated fuel cycle facility. Both the basic concept and the technology base have been demonstrated through actual integral cycle operation in EBR-II. This paper discusses the inherent safety characteristics of the IFR concept

  8. Guide to research facilities

    Energy Technology Data Exchange (ETDEWEB)

    1993-06-01

    This Guide provides information on facilities at US Department of Energy (DOE) and other government laboratories that focus on research and development of energy efficiency and renewable energy technologies. These laboratories have opened these facilities to outside users within the scientific community to encourage cooperation between the laboratories and the private sector. The Guide features two types of facilities: designated user facilities and other research facilities. Designated user facilities are one-of-a-kind DOE facilities that are staffed by personnel with unparalleled expertise and that contain sophisticated equipment. Other research facilities are facilities at DOE and other government laboratories that provide sophisticated equipment, testing areas, or processes that may not be available at private facilities. Each facility listing includes the name and phone number of someone you can call for more information.

  9. Facility design consequences of different employees’ quality perceptions

    NARCIS (Netherlands)

    Kok, Herman; Mobach, Mark P.; Omta, Onno

    2015-01-01

    An important challenge for facility management is to integrate the complex and comprehensive construct of different service processes and physical elements of the service facility into a meaningful and functional facility design. The difficulty of this task is clearly indicated by the present study

  10. The Australian National Proton Facility

    International Nuclear Information System (INIS)

    Jackson, M.; Rozenfeld, A.; Bishop, J.

    2002-01-01

    Full text: Protons have been used in the treatment of cancer since 1954 and over 30,000 patients have been treated around the world. Their precise dose distribution allows the treatment of small tumours in critical locations such as the base of skull and orbit and is an alternative to stereotactic radiotherapy in other sites. With the development of hospital-based systems in the 1990's, common tumours such as prostate, breast and lung cancer can now also be treated using simple techniques. The therapeutic ratio is improved as the dose to the tumour can be increased while sparing normal tissues. The well defined high dose region and low integral dose compared with photon treatments is a particular advantage in children and other situations where long-term survival is expected and when used in combination with chemotherapy. In January 2002, the NSW Health Department initiated a Feasibility Study for an Australian National Proton Facility. This Study will address the complex medical, scientific, engineering, commercial and legal issues required to design and build a proton facility in Australia. The Facility will be mainly designed for patient treatment but will also provide facilities for biological, physical and engineering research. The proposed facility will have a combination of fixed and rotating beams with an energy range of 70-250 MeV. Such a centre will enable the conduct of randomised clinical trials and a comparison with other radiotherapy techniques such as Intensity Modulated Radiation Therapy. Cost-utility comparisons with other medical treatments will also be made and further facilities developed if the expected benefit is confirmed. When patients are not being treated, the beam will be available for commercial and research purposes. This presentation will summarize the progress of the Study and discuss the important issues that need to be resolved before the Facility is approved and constructed

  11. Communication grounding facility

    International Nuclear Information System (INIS)

    Lee, Gye Seong

    1998-06-01

    It is about communication grounding facility, which is made up twelve chapters. It includes general grounding with purpose, materials thermal insulating material, construction of grounding, super strength grounding method, grounding facility with grounding way and building of insulating, switched grounding with No. 1A and LCR, grounding facility of transmission line, wireless facility grounding, grounding facility in wireless base station, grounding of power facility, grounding low-tenton interior power wire, communication facility of railroad, install of arrester in apartment and house, install of arrester on introduction and earth conductivity and measurement with introduction and grounding resistance.

  12. Australian national proton facility

    International Nuclear Information System (INIS)

    Jackson, M.

    2000-01-01

    Full text: Proton therapy has been in use since 1954 and over 25,000 patients have been treated worldwide. Until recently most patients were treated at physics research facilities and apart from the Harvard Cyclotron Laboratory and some low energy machines for eye treatment, only small numbers of patients were treated in each centre and conditions were less than optimal. Limited beam time and lack of support facilities restricted the type of patient treated and conventional fractionation could not be used. The initial clinical experience was mainly with small tumours and other lesions close to critical organs. Large numbers of eye tumours have also been treated. Protons have a well-defined role in these situations and are now being used in the treatment of more common cancers. Since the development of hospital-based facilities, such as the one in Loma Linda in California, over 2,500 patients with prostate cancer have been treated using a simple technique which gives results at least as good as radical surgery, external beam radiotherapy or brachytherapy. Importantly, the incidence of severe complications is very low. There are encouraging results in many disease sites including lung, liver, soft tissue sarcomas and oesophagus. As proton therapy becomes more widely available, randomised trials comparing it with conventional radiotherapy or intensity modulated radiotherapy (IMRT) will be possible. In most situations the use of protons will enable a higher dose to be given safely but in situations where local control rates are already satisfactory, protons are expected to produce less complications than conventional treatment. The initial costs of a proton facility are high but the recurrent costs are similar to other forms of high technology radiotherapy. Simple treatment techniques with only a few fields are usually possible and proton therapy avoids the high integral doses associated with IMRT. This reduction in the low dose volume is likely to be particularly

  13. AOV Facility Tool/Facility Safety Specifications -

    Data.gov (United States)

    Department of Transportation — Develop and maintain authorizing documents that are standards that facilities must follow. These standards are references of FAA regulations and are specific to the...

  14. Facility effluent monitoring plan for the tank farms facilities

    International Nuclear Information System (INIS)

    Crummel, G.M.; Gustavson, R.D.; Kenoyer, J.L.; Moeller, M.P.

    1991-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum three years. A variety of liquid wastes are generated in processing treatment, and disposal operations throughout the Hanford Site. The Tank Farms Project serves a major role in Hanford Site waste management activities as the temporary repository for these wastes. Stored wastes include hazardous components regulated under the Resource Conservation and Recovery Act of 1976 (RCRA) and as by-product material regulated under the Atomic Energy Act of 1954. A total of 177 single- and double-shell tanks (SST and DST) have been constructed in the 200 East and 200 West Areas of the Hanford Site. These facilities were constructed to various designs from 1943 to 1986. The Tank Farms Project is comprised of these tanks along with various transfer, receiving, and treatment facilities

  15. Renewable Electricity-to-Grid Integration | Energy Systems Integration

    Science.gov (United States)

    Facility | NREL Renewable Electricity-to-Grid Integration Renewable Electricity-to-Grid Integration NREL works with industry partners to optimize strategies for effectively interconnecting renewable renewable electric grid integration work includes research and development (R&D) on advanced inverters

  16. Space shuttle operations integration plan

    Science.gov (United States)

    1975-01-01

    The Operations Integration Plan is presented, which is to provide functional definition of the activities necessary to develop and integrate shuttle operating plans and facilities to support flight, flight control, and operations. It identifies the major tasks, the organizations responsible, their interrelationships, the sequence of activities and interfaces, and the resultant products related to operations integration.

  17. Advanced facilities for radiochemistry at Harwell

    International Nuclear Information System (INIS)

    1985-01-01

    The leaflets in this folder describe the latest addition to Harwell's active handling capability. This is a high level alpha, beta, gamma facility designed specifically for undertaking chemical research and development work. It is based on using high integrity containment boxes which are housed in concrete shielded enclosures. The active boxes can be removed and transferred remotely to a support area where they, and any associated equipment, can be decontaminated and serviced whilst a new fully commissioned box can be readily brought into service. The facility fulfills the principle of ALARA and is sufficiently flexible to accommodate a wide range of active handling requirements. It is supported by a suite of medium active handling cells, radiochemical laboratories and, as necessary, facilities of other scientific and engineering disciplines. The leaflets are: report on conceptual aspects; Techsheet 'Remote handling facility - Salient information'; Techsheet 'Project capabilities'; and 4 sheets of diagrams showing details of the facility. (U.K.)

  18. Design of a hydrogen test facility

    International Nuclear Information System (INIS)

    Morgan, M.J.; Beam, J.E.; Sehmbey, M.S.; Pais, M.R.; Chow, L.C.; Hahn, O.J.

    1992-01-01

    The Air Force has sponsored a program at the University of Kentucky which will lead to a better understanding of the thermal and fluid instabilities during blowdown of supercritical fluids at cryogenic temperatures. An integral part of that program is the design and construction of that hydrogen test facility. This facility will be capable of providing supercritical hydrogen at 30 bars and 35 K at a maximum flow rate of 0.1 kg/s for 90 seconds. Also presented here is an extension of this facility to accommodate the use of supercritical helium

  19. Environmental Protection Agency (EPA) Facility Registry Service (FRS) Emergency Response (ER) Toxic Substances Control Act (TSCA) Facilities - Oil and Hazardous Materials

    Data.gov (United States)

    Department of Homeland Security — The purpose of this web feature service is to provide users with access to integrated facility information from FRS, limited to the subset of facilities that link to...

  20. Evaluation of existing United States' facilities for use as a mixed-oxide (MOX) fuel fabrication facility for plutonium disposition

    International Nuclear Information System (INIS)

    Beard, C.A.; Buksa, J.J.; Chidester, K.; Eaton, S.L.; Motley, F.E.; Siebe, D.A.

    1995-01-01

    A number of existing US facilities were evaluated for use as a mixed-oxide fuel fabrication facility for plutonium disposition. These facilities include the Fuels Material Examination Facility (FMEF) at Hanford, the Washington Power Supply Unit 1 (WNP-1) facility at Hanford, the Barnwell Nuclear Fuel Plant (BNFP) at Barnwell, SC, the Fuel Processing Facility (FPF) at Idaho National Engineering Laboratory (INEL), the Device Assembly Facility (DAF) at the Nevada Test Site (NTS), and the P-reactor at the Savannah River Site (SRS). The study consisted of evaluating each facility in terms of available process space, available building support systems (i.e., HVAC, security systems, existing process equipment, etc.), available regional infrastructure (i.e., emergency response teams, protective force teams, available transportation routes, etc.), and ability to integrate the MOX fabrication process into the facility in an operationally-sound manner that requires a minimum amount of structural modifications

  1. 8. High power laser and ignition facilities

    International Nuclear Information System (INIS)

    Bayramian, A.J.; Beach, R.J.; Bibeau, C.

    2002-01-01

    This document gives a review of the various high power laser projects and ignition facilities in the world: the Mercury laser system and Electra (Usa), the krypton fluoride (KrF) laser and the HALNA (high average power laser for nuclear-fusion application) project (Japan), the Shenguang series, the Xingguang facility and the TIL (technical integration line) facility (China), the Vulcan peta-watt interaction facility (UK), the Megajoule project and its feasibility phase: the LIL (laser integration line) facility (France), the Asterix IV/PALS high power laser facility (Czech Republic), and the Phelix project (Germany). In Japan the 100 TW Petawatt Module Laser, constructed in 1997, is being upgraded to the world biggest peta-watt laser. Experiments have been performed with single-pulse large aperture e-beam-pumped Garpun (Russia) and with high-current-density El-1 KrF laser installation (Russia) to investigate Al-Be foil transmittance and stability to multiple e-beam irradiations. An article is dedicated to a comparison of debris shield impacts for 2 experiments at NIF (national ignition facility). (A.C.)

  2. Lesotho - Health Facility Survey

    Data.gov (United States)

    Millennium Challenge Corporation — The main objective of the 2011 Health Facility Survey (HFS) was to establish a baseline for informing the Health Project performance indicators on health facilities,...

  3. Projectile Demilitarization Facilities

    Data.gov (United States)

    Federal Laboratory Consortium — The Projectile Wash Out Facility is US Army Ammunition Peculiar Equipment (APE 1300). It is a pilot scale wash out facility that uses high pressure water and steam...

  4. Rocketball Test Facility

    Data.gov (United States)

    Federal Laboratory Consortium — This test facility offers the capability to emulate and measure guided missile radar cross-section without requiring flight tests of tactical missiles. This facility...

  5. Wastewater Treatment Facilities

    Data.gov (United States)

    Iowa State University GIS Support and Research Facility — Individual permits for municipal, industrial, and semi-public wastewater treatment facilities in Iowa for the National Pollutant Discharge Elimination System (NPDES)...

  6. Materiel Evaluation Facility

    Data.gov (United States)

    Federal Laboratory Consortium — CRREL's Materiel Evaluation Facility (MEF) is a large cold-room facility that can be set up at temperatures ranging from −20°F to 120°F with a temperature change...

  7. Environmental Toxicology Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Fully-equipped facilities for environmental toxicology researchThe Environmental Toxicology Research Facility (ETRF) located in Vicksburg, MS provides over 8,200 ft...

  8. Dialysis Facility Compare

    Data.gov (United States)

    U.S. Department of Health & Human Services — Dialysis Facility Compare helps you find detailed information about Medicare-certified dialysis facilities. You can compare the services and the quality of care that...

  9. Energetics Conditioning Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Energetics Conditioning Facility is used for long term and short term aging studies of energetic materials. The facility has 10 conditioning chambers of which 2...

  10. Explosive Components Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The 98,000 square foot Explosive Components Facility (ECF) is a state-of-the-art facility that provides a full-range of chemical, material, and performance analysis...

  11. Facilities for US Radioastronomy.

    Science.gov (United States)

    Thaddeus, Patrick

    1982-01-01

    Discusses major developments in radioastronomy since 1945. Topics include proposed facilities, very-long-baseline interferometric array, millimeter-wave telescope, submillimeter-wave telescope, and funding for radioastronomy facilities and projects. (JN)

  12. Neighbourhood facilities for sustainability

    CSIR Research Space (South Africa)

    Gibberd, Jeremy T

    2013-01-01

    Full Text Available . In this paper these are referred to as ‘Neighbourhood Facilities for Sustainability’. Neighbourhood Facilities for Sustainability (NFS) are initiatives undertaken by individuals and communities to build local sustainable systems which not only improve...

  13. Cold Vacuum Drying Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Located near the K-Basins (see K-Basins link) in Hanford's 100 Area is a facility called the Cold Vacuum Drying Facility (CVDF).Between 2000 and 2004, workers at the...

  14. Ouellette Thermal Test Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Thermal Test Facility is a joint Army/Navy state-of-the-art facility (8,100 ft2) that was designed to:Evaluate and characterize the effect of flame and thermal...

  15. Facility design: introduction

    International Nuclear Information System (INIS)

    Unger, W.E.

    1980-01-01

    The design of shielded chemical processing facilities for handling plutonium is discussed. The TRU facility is considered in particular; its features for minimizing the escape of process materials are listed. 20 figures

  16. Integrating palliative care in long-term care facilities across Europe (PACE): protocol of a cluster randomized controlled trial of the 'PACE Steps to Success' intervention in seven countries.

    Science.gov (United States)

    Smets, Tinne; Onwuteaka-Philipsen, Bregje B D; Miranda, Rose; Pivodic, Lara; Tanghe, Marc; van Hout, Hein; Pasman, Roeline H R W; Oosterveld-Vlug, Mariska; Piers, Ruth; Van Den Noortgate, Nele; Wichmann, Anne B; Engels, Yvonne; Vernooij-Dassen, Myrra; Hockley, Jo; Froggatt, Katherine; Payne, Sheila; Szczerbińska, Katarzyna; Kylänen, Marika; Leppäaho, Suvi; Barańska, Ilona; Gambassi, Giovanni; Pautex, Sophie; Bassal, Catherine; Deliens, Luc; Van den Block, Lieve

    2018-03-12

    Several studies have highlighted the need for improvement in palliative care delivered to older people long-term care facilities. However, the available evidence on how to improve palliative care in these settings is weak, especially in Europe. We describe the protocol of the PACE trial aimed to 1) evaluate the effectiveness and cost-effectiveness of the 'PACE Steps to Success' palliative care intervention for older people in long-term care facilities, and 2) assess the implementation process and identify facilitators and barriers for implementation in different countries. We will conduct a multi-facility cluster randomised controlled trial in Belgium, Finland, Italy, the Netherlands, Poland, Switzerland and England. In total, 72 facilities will be randomized to receive the 'Pace Steps to Success intervention' or to 'care as usual'. Primary outcome at resident level: quality of dying (CAD-EOLD); and at staff level: staff knowledge of palliative care (Palliative Care Survey). resident's quality of end-of-life care, staff self-efficacy, self-perceived educational needs, and opinions on palliative care. Economic outcomes: direct costs and quality-adjusted life years (QALYs). Measurements are performed at baseline and after the intervention. For the resident-level outcomes, facilities report all deaths of residents in and outside the facilities over a previous four-month period and structured questionnaires are sent to (1) the administrator, (2) staff member most involved in care (3) treating general practitioner, and (4) a relative. For the staff-level outcomes, all staff who are working in the facilities are asked to complete a structured questionnaire. A process evaluation will run alongside the effectiveness evaluation in the intervention group using the RE-AIM framework. The lack of high quality trials in palliative care has been recognized throughout the field of palliative care research. This cross-national cluster RCT designed to evaluate the impact of the

  17. CLEAR test facility

    CERN Multimedia

    Ordan, Julien Marius

    2017-01-01

    A new user facility for accelerator R&D, the CERN Linear Electron Accelerator for Research (CLEAR), started operation in August 2017. CLEAR evolved from the former CLIC Test Facility 3 (CTF3) used by the Compact Linear Collider (CLIC). The new facility is able to host and test a broad range of ideas in the accelerator field.

  18. Air ventilation/controlling facility

    Energy Technology Data Exchange (ETDEWEB)

    Yoshikawa, Kazuhiro; Kinoshita, Shoichiro

    1997-12-12

    When all electricity supply from the outside of a power plant are lost, a power generator directly connected to an emergency steam turbine which is driven by steams introduced from a nuclear reactor is driven to supply electricity required in the power plant. Cool water prepared by a refrigerator is used as cooling water in an air ventilation/controlling facility of a room equipped with the power generating facility. As the refrigerator, a refrigerator of an existent emergency air cooling water system for an auxiliary air ventilation/controlling equipment is used. This can extend the period of time till the temperature of the room where the power generator is disposed exceeds the temperature range capable of keeping the integrity of the power generator even when all the AC power supply are lost to inactivate the function of the air ventilation/controlling system. (I.S.)

  19. Security of pipeline facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, S.C. [Alberta Energy and Utilities Board, Calgary, AB (Canada); Van Egmond, C.; Duquette, L. [National Energy Board, Calgary, AB (Canada); Revie, W. [Canada Centre for Mineral and Energy Technology, Ottawa, ON (Canada)

    2005-07-01

    This working group provided an update on provincial, federal and industry directions regarding the security of pipeline facilities. The decision to include security issues in the NEB Act was discussed as well as the Pipeline Security Management Assessment Project, which was created to establish a better understanding of existing security management programs as well as to assist the NEB in the development and implementation of security management regulations and initiatives. Amendments to the NEB were also discussed. Areas of pipeline security management assessment include physical safety management; cyber and information security management; and personnel security. Security management regulations were discussed, as well as implementation policies. Details of the Enbridge Liquids Pipelines Security Plan were examined. It was noted that the plan incorporates flexibility for operations and is integrated with Emergency Response and Crisis Management. Asset characterization and vulnerability assessments were discussed, as well as security and terrorist threats. It was noted that corporate security threat assessment and auditing are based on threat information from the United States intelligence community. It was concluded that the oil and gas industry is a leader in security in North America. The Trans Alaska Pipeline Incident was discussed as a reminder of how costly accidents can be. Issues of concern for the future included geographic and climate issues. It was concluded that limited resources are an ongoing concern, and that the regulatory environment is becoming increasingly prescriptive. Other concerns included the threat of not taking international terrorism seriously, and open media reporting of vulnerability of critical assets, including maps. tabs., figs.

  20. Facility or Facilities? That is the Question.

    Science.gov (United States)

    Viso, M.

    2018-04-01

    The management of the martian samples upon arrival on the Earth will require a lot of work to ensure a safe life detection and biohazard testing during the quarantine. This will induce a sharing of the load between several facilities.