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Sample records for power facility sandusky

  1. Independent Confirmatory Survey Summary and Results for the Plum Brook Reactor Facility Sandusky OH

    International Nuclear Information System (INIS)

    Bailey, E.N.

    2008-01-01

    In 1941, the War Department acquired approximately 9,000 acres of land near Sandusky, Ohio and constructed a munitions plant. The Plum Brook Ordnance Works Plant produced munitions, such as TNT, until the end of World War II. Following the war, the land remained idle until the National Advisory Committee for Aeronautics (later known as the National Aeronautics and Space Administration or NASA) obtained 500 acres to construct a nuclear research reactor designed to study the effects of radiation on materials used in space flight. The research reactor was put into operation in 1961 and was the first of fifteen test facilities eventually built by NASA at the Plum Brook Station. By 1963, NASA had acquired the remaining land at Plum Brook for these additional test facilities. After successfully completing the objective of landing humans on the Moon and returning them safely to Earth, NASA was faced with budget reductions from Congress in 1973. These budgetary constraints caused NASA to cease operations at several research facilities across the country, including those at Plum Brook Station. The major test facilities at Plum Brook were maintained in a standby mode, capable of being reactivated for future use. The Plum Brook Reactor Facility (PBRF) was shut down January 5, 1973 and all of the nuclear fuel was eventually removed and shipped off site to a U.S. Department of Energy facility in Idaho for disposal or reuse. Decommissioning activities are currently underway at the PBRF (NASA 1999). The objectives of the confirmatory survey activities were to provide independent contractor field data reviews and to generate independent radiological data for use by the Nuclear Regulatory Commission (NRC) in evaluating the adequacy and accuracy of the licensee's procedures and final status survey (FSS) results

  2. Arsenic Removal from Drinking Water by Coagulation/Filtration U.S. EPA Demonstration Project at Sandusky, MI. Six-Month Evaluation Report

    Science.gov (United States)

    This report documents the activities performed during and the results obtained from the first six months of the EPA arsenic removal technology demonstration project at the City of Sandusky, MI facility. The objectives of the project are to evaluate 1) the effectiveness of Siemen...

  3. Final-Independent Confirmatory Survey Report For The Reactor Building, Hot Laboratory, Primary Pump House, And Land Areas At The Plum Brook Reactor Facility, Sandusky, Ohio DCN:2036-SR-01-10

    International Nuclear Information System (INIS)

    Bailey, Erika N.

    2011-01-01

    In 1941, the War Department acquired approximately 9,000 acres of land near Sandusky, Ohio and constructed a munitions plant. The Plum Brook Ordnance Works Plant produced munitions, such as TNT, until the end of World War II. Following the war, the land remained idle until the National Advisory Committee for Aeronautics later called the National Aeronautics and Space Administration (NASA) obtained 500 acres to construct a nuclear research reactor designed to study the effects of radiation on materials used in space flight. The research reactor was put into operation in 1961 and was the first of fifteen test facilities eventually built by NASA at the Plum Brook Station. By 1963, NASA had acquired the remaining land at Plum Brook for these additional test facilities

  4. Nitrogen cycling in Sandusky Bay, Lake Erie: oscillations between strong and weak export and implications for harmful algal blooms

    Science.gov (United States)

    Salk, Kateri R.; Bullerjahn, George S.; McKay, Robert Michael L.; Chaffin, Justin D.; Ostrom, Nathaniel E.

    2018-05-01

    Recent global water quality crises point to an urgent need for greater understanding of cyanobacterial harmful algal blooms (cHABs) and their drivers. Nearshore areas of Lake Erie such as Sandusky Bay may become seasonally limited by nitrogen (N) and are characterized by distinct cHAB compositions (i.e., Planktothrix over Microcystis). This study investigated phytoplankton N uptake pathways, determined drivers of N depletion, and characterized the N budget in Sandusky Bay. Nitrate (NO3-) and ammonium (NH4+) uptake, N fixation, and N removal processes were quantified by stable isotopic approaches. Dissimilatory N reduction was a relatively modest N sink, with denitrification, anammox, and N2O production accounting for 84, 14, and 2 % of sediment N removal, respectively. Phytoplankton assimilation was the dominant N uptake mechanism, and NO3- uptake rates were higher than NH4+ uptake rates. Riverine N loading was sometimes insufficient to meet assimilatory and dissimilatory demands, but N fixation alleviated this deficit. N fixation made up 23.7-85.4 % of total phytoplankton N acquisition and indirectly supports Planktothrix blooms. However, N fixation rates were surprisingly uncorrelated with NO3- or NH4+ concentrations. Owing to temporal separation in sources and sinks of N to Lake Erie, Sandusky Bay oscillates between a conduit and a filter of downstream N loading to Lake Erie, delivering extensively recycled forms of N during periods of low export. Drowned river mouths such as Sandusky Bay are mediators of downstream N loading, but climate-change-induced increases in precipitation and N loading will likely intensify N export from these systems.

  5. 76 FR 55564 - Safety Zone; Revolution 3 Triathlon, Sandusky Bay, Lake Erie, Cedar Point, OH

    Science.gov (United States)

    2011-09-08

    ...-AA00 Safety Zone; Revolution 3 Triathlon, Sandusky Bay, Lake Erie, Cedar Point, OH AGENCY: Coast Guard... Erie during the Revolution 3 Triathlon. This temporary safety zone is necessary to protect participants..., between 9 a.m. and 5 p.m., Monday through Friday, except Federal holidays. FOR FURTHER INFORMATION CONTACT...

  6. 75 FR 55477 - Safety Zone; Revolution 3 Triathlon, Lake Erie & Sandusky Bay, Cedar Point, OH

    Science.gov (United States)

    2010-09-13

    ...-AA00 Safety Zone; Revolution 3 Triathlon, Lake Erie & Sandusky Bay, Cedar Point, OH AGENCY: Coast Guard... portions of the Lake Erie during the Revolution 3 Cedar Point Triathlon. The temporary safety zone is... 5 p.m., Monday through Friday, except Federal holidays. FOR FURTHER INFORMATION CONTACT: If you have...

  7. Thermal and Hydraulic Conditions Supporting the Recruitment of Asian Carp in Seiche Affected Rivers of Lake Erie Basin - A Case Study of the Lower Sandusky River in Ohio

    Science.gov (United States)

    Soong, D. T.; Santacruz, S.; Jones, L.; Garcia, T.; Kočovský, P. M.; Embke, H.

    2017-12-01

    Grass Carp Ctenopharyngodon idella (Cyprinidae) is an invasive fish species that spawns in rivers during high-flow events. In their native range, it is believed eggs must hatch within the riverine environment in order to eventually result in production of adult fish. The lower Sandusky River is approximately 26 km long extending from its confluence with Sandusky Bay upstream to the Ballville Dam, which is impassible for Grass Carp. Grass Carp are known to have spawned in the Sandusky River, a tributary to Lake Erie, in 2011, 2013, 2015, and 2017. This study characterizes the thermal and hydraulic conditions under which these eggs could hatch in the lower Sandusky River, a relatively short river reach for egg hatching. Grass Carp eggs collected in 2015 were previously analyzed for hatching locations using a one-dimensional steady-state HEC-RAS hydraulic model. In this study we refine estimates of hatching locations by incorporating the influence of fluctuating water levels downstream due to seiches in Lake Erie and overland and tributary inflows using an unsteady 1D/2D HEC-RAS hydraulic model. Additionally, conditions conducive to successful hatching, which occurs when eggs reach the hatching stage within the river, were analyzed from nine high-flow events between 2011 and 2015. Simulated hydraulic and water temperature data were used as inputs to the Fluvial Egg Drift Simulator (FluEgg) model, which was used to analyze the transport and dispersal of Grass carp eggs until hatching. We will describe the differences in steady- and unsteady-state hydraulic modeling in predicting hatching locations of Grass Carp eggs for the 2015 spawning events. Results will also include hydraulic and temperature variables that contribute to the successful/unsuccessful in-river hatching for the nine flow events simulated.

  8. Structural Dynamic Assessment of the GN2 Piping System for NASA's New and Powerful Reverberant Acoustic Test Facility

    Science.gov (United States)

    McNelis, Mark E.; Staab, Lucas D.; Akers, James C.; Hughes, WIlliam O.; Chang, Li, C.; Hozman, Aron D.; Henry, Michael W.

    2012-01-01

    The National Aeronautics and Space Administration (NASA) Glenn Research Center (GRC) has led the design and build of the new world-class vibroacoustic test capabilities at the NASA GRC's Plum Brook Station in Sandusky, Ohio, USA from 2007-2011. SAIC-Benham has completed construction of a new reverberant acoustic test facility to support the future testing needs of NASA's space exploration program and commercial customers. The large Reverberant Acoustic Test Facility (RATF) is approximately 101,000 cu ft in volume and was designed to operate at a maximum empty chamber acoustic overall sound pressure level (OASPL) of 163 dB. This combination of size and acoustic power is unprecedented amongst the world's known active reverberant acoustic test facilities. Initial checkout acoustic testing was performed on March 2011 by SAIC-Benham at test levels up to 161 dB OASPL. During testing, several branches of the gaseous nitrogen (GN2) piping system, which supply the fluid to the noise generating acoustic modulators, failed at their "t-junctions" connecting the 12 inch supply line to their respective 4 inch branch lines. The problem was initially detected when the oxygen sensors in the horn room indicated a lower than expected oxygen level from which was inferred GN2 leaks in the piping system. In subsequent follow up inspections, cracks were identified in the failed "t-junction" connections through non-destructive evaluation testing . Through structural dynamic modeling of the piping system, the root cause of the "t-junction" connection failures was determined. The structural dynamic assessment identified several possible corrective design improvements to the horn room piping system. The effectiveness of the chosen design repairs were subsequently evaluated in September 2011 during acoustic verification testing to 161 dB OASPL.

  9. Power Electronics and Electric Machines Facilities | Transportation

    Science.gov (United States)

    Research | NREL Facilities Power Electronics and Electric Machines Facilities NREL's power electronics and electric machines thermal management experimentation facilities feature a wide range of four researchers in discussion around a piece of laboratory equipment. Power electronics researchers

  10. Power source facility

    Energy Technology Data Exchange (ETDEWEB)

    Yoshikawa, Kazuhiro; Kinoshita, Shoichiro

    1998-09-29

    The present invention concerns a power plant, in which power is supplied from an ordinary system battery to an ordinary DC bus system when all of the AC power sources should be lost and a generator is driven by a steam turbine. A generator is connected with an ordinary system battery charger by way of a channel. If all of power sources should be lost, the ordinary system battery charger is driven by using emergency steam turbine generator facilities, and reactor steams are supplied thereby enabling to supply power to the ordinary system DC bus system for a long period of time. (N.H.)

  11. Gingin High Optical Power Test Facility

    International Nuclear Information System (INIS)

    Zhao, C; Blair, D G; Barrigo, P

    2006-01-01

    The Australian Consortium for Gravitational Wave Astronomy (ACIGA) in collaboration with LIGO is developing a high optical power research facility at the AIGO site, Gingin, Western Australia. Research at the facility will provide solutions to the problems that advanced gravitational wave detectors will encounter with extremely high optical power. The problems include thermal lensing and parametric instabilities. This article will present the status of the facility and the plan for the future experiments

  12. The Testing Behind The Test Facility: The Acoustic Design of the NASA Glenn Research Center's World-Class Reverberant Acoustic Test Facility

    Science.gov (United States)

    Hozman, Aron D.; Hughes, William O.; McNelis, Mark E.; McNelis, Anne M.

    2011-01-01

    The National Aeronautics and Space Administration (NASA) Glenn Research Center (GRC) is leading the design and build of the new world-class vibroacoustic test capabilities at the NASA GRC's Plum Brook Station in Sandusky, Ohio, USA. Benham Companies, LLC is currently constructing modal, base-shake sine and reverberant acoustic test facilities to support the future testing needs of NASA's space exploration program. The large Reverberant Acoustic Test Facility (RATF) will be approximately 101,000 cu ft in volume and capable of achieving an empty chamber acoustic overall sound pressure level (OASPL) of 163 dB. This combination of size and acoustic power is unprecedented amongst the world's known active reverberant acoustic test facilities. The key to achieving the expected acoustic test spectra for a range of many NASA space flight environments in the RATF is the knowledge gained from a series of ground acoustic tests. Data was obtained from several NASA-sponsored test programs, including testing performed at the National Research Council of Canada's acoustic test facility in Ottawa, Ontario, Canada, and at the Redstone Technical Test Center acoustic test facility in Huntsville, Alabama, USA. The majority of these tests were performed to characterize the acoustic performance of the modulators (noise generators) and representative horns that would be required to meet the desired spectra, as well as to evaluate possible supplemental gas jet noise sources. The knowledge obtained in each of these test programs enabled the design of the RATF sound generation system to confidently advance to its final acoustic design and subsequent on-going construction.

  13. Design of radioisotope power systems facility

    International Nuclear Information System (INIS)

    Eschenbaum, R.C.; Wiemers, M.J.

    1991-01-01

    Radioisotope power systems currently produced for the U.S. Department of Energy Office of Special Applications by the Mound Laboratory at Miamisburg, Ohio, have been used in a variety of configurations by the Department of Defense and the National Aeronautics and Space Administration. A forecast of fugure radioisotope power systems requirements showed a need for an increased production rate beyond the capability of the existing Mound Laboratory. Westinghouse Hanford Company is modifying the Fuels and Materials Examination Facility on the Hanford Site near Richland, Washington, to install the new Radioisotope Power Systems Facility for assembling future radioisotope power systems. The facility is currently being prepared to assemble the radioisotope thermoelectric generators required by the National Aeronautics and Space Administration missions for Comet Rendezvous Asteroid Flyby in 1995 and Cassini, an investigation of Saturn and its moons, in 1996

  14. Power Systems Development Facility

    International Nuclear Information System (INIS)

    1993-06-01

    The objective of the PSDF would be to provide a modular facility which would support the development of advanced, pilot-scale, coal-based power systems and hot gas clean-up components. These pilot-scale components would be designed to be large enough so that the results can be related and projected to commercial systems. The facility would use a modular approach to enhance the flexibility and capability for testing; consequently, overall capital and operating costs when compared with stand-alone facilities would be reduced by sharing resources common to different modules. The facility would identify and resolve technical barrier, as well as-provide a structure for long-term testing and performance assessment. It is also intended that the facility would evaluate the operational and performance characteristics of the advanced power systems with both bituminous and subbituminous coals. Five technology-based experimental modules are proposed for the PSDF: (1) an advanced gasifier module, (2) a fuel cell test module, (3) a PFBC module, (4) a combustion gas turbine module, and (5) a module comprised of five hot gas cleanup particulate control devices. The final module, the PCD, would capture coal-derived ash and particles from both the PFBC and advanced gasifier gas streams to provide for overall particulate emission control, as well as to protect the combustion turbine and the fuel cell

  15. 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.)

  16. Space Power Facility (SPF)

    Data.gov (United States)

    Federal Laboratory Consortium — The Space Power Facility (SPF) houses the world's largest space environment simulation chamber, measuring 100 ft. in diameter by 122 ft. high. In this chamber, large...

  17. High Power RF Test Facility at the SNS

    CERN Document Server

    Kang, Yoon W; Campisi, Isidoro E; Champion, Mark; Crofford, Mark; Davis, Kirk; Drury, Michael A; Fuja, Ray E; Gurd, Pamela; Kasemir, Kay-Uwe; McCarthy, Michael P; Powers, Tom; Shajedul Hasan, S M; Stirbet, Mircea; Stout, Daniel; Tang, Johnny Y; Vassioutchenko, Alexandre V; Wezensky, Mark

    2005-01-01

    RF Test Facility has been completed in the SNS project at ORNL to support test and conditioning operation of RF subsystems and components. The system consists of two transmitters for two klystrons powered by a common high voltage pulsed converter modulator that can provide power to two independent RF systems. The waveguides are configured with WR2100 and WR1150 sizes for presently used frequencies: 402.5 MHz and 805 MHz. Both 402.5 MHz and 805 MHz systems have circulator protected klystrons that can be powered by the modulator capable of delivering 11 MW peak and 1 MW average power. The facility has been equipped with computer control for various RF processing and complete dual frequency operation. More than forty 805 MHz fundamental power couplers for the SNS superconducting linac (SCL) cavitites have been RF conditioned in this facility. The facility provides more than 1000 ft2 floor area for various test setups. The facility also has a shielded cave area that can support high power tests of normal conducti...

  18. New facility for testing LHC HTS power leads

    CERN Document Server

    Rabehl, Roger Jon; Fehér, S; Huang, Y; Orris, D; Pischalnikov, Y; Sylvester, C D; Tartaglia, M

    2005-01-01

    A new facility for testing HTS power leads at the Fermilab Magnet Test Facility has been designed and operated. The facility has successfully tested 19 pairs of HTS power leads, which are to be integrated into the Large Hadron Collider Interaction Region cryogenic feed boxes. This paper describes the design and operation of the cryogenics, process controls, data acquisition, and quench management systems. HTS power lead test results from the commissioning phase of the project are also presented.

  19. Power facility plan and power supply plan of Japan in 1988

    Energy Technology Data Exchange (ETDEWEB)

    Yoshino, Shoji; Makino, Masao

    1988-06-01

    The power facility plan and the power supply plan for 1988 are described. The demand by non-industrial use will grow at an average of 3.8% for the 1986-97 period due to changes in the life style, construction and extension of buildings and increasing use of OA equipment although the power conservation is promoted. The industrial consumption will increase at only 1.2% a year due to the slowed growth and energy saving. As a result, the total demand will be 778,200 million kWh in 1997 with annual growth of 2.4%. The maximum demand will be 151,210 kW in 1997 with annual growth of 2.9%. The annual load rate will decrease to 56.9%, showing a continuously worsening utilization efficiency of power facilities. The development of 29 power units with total capacity of 2,760 MW is planned in 1988 for a stable power supply with a sufficient margin regarding maximum demand. The plan requires the investment of 3,700 billion yen, including the power transmission systems and substations. The power supply plan in 1988 is aimed at the effective operation of facilities and cost reduction by regional management under proper recognition of local characteristics of each power source, while maintaining a stable power supply with specified margins. (1 fig, 11 tabs)

  20. Optimum operation of a small power production facility

    Energy Technology Data Exchange (ETDEWEB)

    Capehart, B.L.; Mahoney, J.F.; Sivazlian, B.D.

    1983-09-01

    To help reduce the U.S.A.'s dependence on imported oil for electrical power generation, the 1978 National Energy Act established regulations to promote construction and operation of cogeneration and small power production facilities. Many of these facilities are presently under construction, with a great number planned. This paper examines the operation of a small power production facility with on-site generation and storage, on-site use, and connection to an electric utility grid system for the purpose of both selling excess power and buying power. It is assumed that the buying and selling price of electricity varies frequently during the day and that the relevant price and demand data may be accurately projected into the near future. With this system description, a mathematical model is formulated and solved by linear programming to obtain a series of periodic buy and sell decisions so as to maximize the profit from operating the small power production facility. Results are presented to illustrate the methodology for determining potential profits.

  1. Lewis Research Center space station electric power system test facilities

    Science.gov (United States)

    Birchenough, Arthur G.; Martin, Donald F.

    1988-01-01

    NASA Lewis Research Center facilities were developed to support testing of the Space Station Electric Power System. The capabilities and plans for these facilities are described. The three facilities which are required in the Phase C/D testing, the Power Systems Facility, the Space Power Facility, and the EPS Simulation Lab, are described in detail. The responsibilities of NASA Lewis and outside groups in conducting tests are also discussed.

  2. Backup power sources for DOE facilities

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

    This standard establishes fundamental requirements and guidance for backup power sources at DOE facilities. Purpose is to document good engineering practices for installation, testing, and maintenance of these backup power sources, which also covers emergency power sources. Examples are those which supply power to nuclear safety systems, radiation monitors and alarms, fire protection systems, security systems, and emergency lighting.

  3. Energy Systems Test Area (ESTA). Power Systems Test Facilities

    Science.gov (United States)

    Situ, Cindy H.

    2010-01-01

    This viewgraph presentation provides a detailed description of the Johnson Space Center's Power Systems Facility located in the Energy Systems Test Area (ESTA). Facilities and the resources used to support power and battery systems testing are also shown. The contents include: 1) Power Testing; 2) Power Test Equipment Capabilities Summary; 3) Source/Load; 4) Battery Facilities; 5) Battery Test Equipment Capabilities Summary; 6) Battery Testing; 7) Performance Test Equipment; 8) Battery Test Environments; 9) Battery Abuse Chambers; 10) Battery Abuse Capabilities; and 11) Battery Test Area Resources.

  4. Feasibility Investigation for a Solar Power Generation Facility

    Science.gov (United States)

    Nathan, Lakshmi

    2010-01-01

    The Energy Policy Act of 2005 states that by fiscal year 2013, at least 7.5% of the energy consumed by the government must be renewable energy. In an effort to help meet this goal, Johnson Space Center (JSC) is considering installing a solar power generation facility. The purpose of this project is to conduct a feasibility investigation for such a facility. Because Kennedy Space Center (KSC) has a solar power generation facility, the first step in this investigation is to learn about KSC's facility and obtain information on how it was constructed. After collecting this information, the following must be determined: the amount of power desired, the size of the facility, potential locations for it, and estimated construction and maintenance costs. Contacts with JSC's energy provider must also be established to determine if a partnership would be agreeable to both parties. Lastly, all of this data must be analyzed to decide whether or not JSC should construct the facility. The results from analyzing the data collected indicate that a 200 kW facility would provide enough energy to meet 1% of JSC's energy demand. This facility would require less than 1 acre of land. In the map below, potential locations are shown in green. The solar power facility is projected to cost $2 M. So far, the information collected indicates that such a facility could be constructed. The next steps in this investigation include contacting JSC's energy provider, CenterPoint Energy, to discuss entering a partnership; developing a life cycle cost analysis to determine payback time; developing more detailed plans; and securing funding.

  5. Outline of electric power facility plan in fiscal year 1988

    International Nuclear Information System (INIS)

    1988-01-01

    As to the electric power facility plan in fiscal year 1988, 15 designated electric power enterprises made the notification to the Minister of International Trade and Industry in March, 1988. This outline of the facility plan summarized the plans of 66 enterprises in total, including the plans of municipally operated, joint thermal power and other enterprises in addition to the above 15. In order to ensure the stable supply of electric power, the Ministry of International Trade and Industry considers that it is indispensable to purposefully develop electric power sources and the facilities for distribution along this facility plan. The forecast for fiscal year 1997 is : total electric power demand 778.2 billion kWh, maximum power demand 151.21 million kW, and yearly load factor 56.9 %. This is equivalent to the yearly growth of 2.4 %. In fiscal year 1988, it is planned to present 29 plants of 2760 MW to the Power Source Development Coordination Council. The breakdown is : hydroelectricity 140 MW, thermal power 2010 MW, and nuclear power 610 MW. The Ministry guides electric power enterprises so as to realize the diversification of electric power sources. Also the increase of transmission and transformation facilities, the plan of equipment investment and others are reported. (Kako, I.)

  6. 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

  7. Power Systems Development Facility

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2009-01-31

    In support of technology development to utilize coal for efficient, affordable, and environmentally clean power generation, the Power Systems Development Facility (PSDF), located in Wilsonville, Alabama, has routinely demonstrated gasification technologies using various types of coals. The PSDF is an engineering scale demonstration of key features of advanced coal-fired power systems, including a Transport Gasifier, a hot gas particulate control device, advanced syngas cleanup systems, and high-pressure solids handling systems. This final report summarizes the results of the technology development work conducted at the PSDF through January 31, 2009. Twenty-one major gasification test campaigns were completed, for a total of more than 11,000 hours of gasification operation. This operational experience has led to significant advancements in gasification technologies.

  8. Prospects for high-power radioactive beam facilities worldwide

    CERN Document Server

    Nolen, Jerry A

    2003-01-01

    Advances in accelerators, targets, ion sources, and experimental instrumentation are making possible ever more powerful facilities for basic and applied research with short-lived radioactive isotopes. There are several current generation facilities, based on a variety of technologies, operating worldwide. These include, for example, those based on the in-flight method such as the recently upgraded National Superconducting Cyclotron Laboratory at Michigan State University, the facility at RIKEN in Japan, GANIL in Caen, France, and GSI in Darmstadt, Germany. Present facilities based on the Isotope-Separator On-Line method include, for example, the ISOLDE laboratory at CERN, HRIBF at Oak Ridge, and the new high-power facility ISAC at TRIUMF in Vancouver. Next-generation facilities include the Radioactive-Ion Factory upgrade of RIKEN to higher energy and intensity and the upgrade of ISAC to a higher energy secondary beam; both of these projects are in progress. A new project, LINAG, to upgrade the capabilities at...

  9. Effective use of electric power facilities and promotion of energy conservation

    International Nuclear Information System (INIS)

    Tokumitsu, Iwao

    1999-01-01

    The capacity of Japan's commercial electric power facilities has been increased to more than 200 million kw. In order to provide a stable supply of electric power to meet constantly fluctuaring electric power demands, Japan's power plants generate electricity using an optimal combination of facilities, with nuclear power and coal-fired thermoelectric power providing the base load supply. In the use of electric power, moreover, measures are being implemented to reduce generation costs, conserve energy, and cut carbon dioxide emissions by reducing maximum output and equalizing the load. This report presents information concerning measures for improving the efficiency of electric power facilities operation, equalizing the load and promoting energy conservation. (author)

  10. 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

  11. The Development of the Acoustic Design of NASA Glenn Research Center's New Reverberant Acoustic Test Facility

    Science.gov (United States)

    Hughes, William O.; McNelis, Mark E.; Hozman, Aron D.; McNelis, Anne M.

    2011-01-01

    The National Aeronautics and Space Administration (NASA) Glenn Research Center (GRC) is leading the design and build of the new world-class vibroacoustic test capabilities at the NASA GRC s Plum Brook Station in Sandusky, Ohio. Benham Companies, LLC is currently constructing modal, base-shake sine and reverberant acoustic test facilities to support the future testing needs of NASA s space exploration program. The large Reverberant Acoustic Test Facility (RATF) will be approximately 101,000 ft3 in volume and capable of achieving an empty chamber acoustic overall sound pressure level (OASPL) of 163 dB. This combination of size and acoustic power is unprecedented amongst the world s known active reverberant acoustic test facilities. The key to achieving the expected acoustic test spectra for a range of many NASA space flight environments in the RATF is the knowledge gained from a series of ground acoustic tests. Data was obtained from several NASA-sponsored test programs, including testing performed at the National Research Council of Canada s acoustic test facility in Ottawa, Ontario, Canada, and at the Redstone Technical Test Center acoustic test facility in Huntsville, Alabama. The majority of these tests were performed to characterize the acoustic performance of the modulators (noise generators) and representative horns that would be required to meet the desired spectra, as well as to evaluate possible supplemental gas jet noise sources. The knowledge obtained in each of these test programs enabled the design of the RATF sound generation system to confidently advance to its final acoustic design and subsequent on-going construction.

  12. ACIGA's high optical power test facility

    International Nuclear Information System (INIS)

    Ju, L; Aoun, M; Barriga, P

    2004-01-01

    Advanced laser interferometer detectors utilizing more than 100 W of laser power and with ∼10 6 W circulating laser power present many technological problems. The Australian Consortium for Interferometric Gravitational Astronomy (ACIGA) is developing a high power research facility in Gingin, north of Perth, Western Australia, which will test techniques for the next generation interferometers. In particular it will test thermal lensing compensation and control strategies for optical cavities in which optical spring effects and parametric instabilities may present major difficulties

  13. On-site electric power source facility for Japanese nuclear power plant

    International Nuclear Information System (INIS)

    Oohara, T.

    1986-01-01

    Trends of construction of nuclear power plants in Japan, occurrence rate of incidents/failures of electric facilities, major example of incidents/failures, their countermeasure to prevent recurrence are introduced. Furthermore, safety administration system of the Government, electric utilities and manufacturers, and various countermeasures to prevent incident/ failure of electrical facilities from the hardware and software sides are discussed. (author)

  14. On-site electric power source facility for Japanese nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Oohara, T. [Incident/Failure Analysis and Evaluation Office, Nuclear Power Safety Information Research Centre, Nuclear Power Engineering Test Centre, 2nd Floor, Shuwa-Kamiyacho Bldg., 3-13, 4-Chome, Toranomon Minato-ku, Tokyo 105 (Japan)

    1986-02-15

    Trends of construction of nuclear power plants in Japan, occurrence rate of incidents/failures of electric facilities, major example of incidents/failures, their countermeasure to prevent recurrence are introduced. Furthermore, safety administration system of the Government, electric utilities and manufacturers, and various countermeasures to prevent incident/ failure of electrical facilities from the hardware and software sides are discussed. (author)

  15. Optimised deployment of hydro-power generation facilities

    International Nuclear Information System (INIS)

    Werlen, K.

    2004-01-01

    This article discusses how the opening-up of the European electricity market has led to the creation of more room for manoeuvre in the deployment of the generation capacity of dam and pumped-storage-based hydropower facilities and low-head power stations. Software tools for the optimisation of the operation of power generation facilities that can take care of complex hydraulic interdependencies are described. The use of the software for the assessment of new installations being planned or of older installations being extended is examined. The influence of climatic conditions, market prices for power, the general requirements placed on the system and other influences on financial gain are looked at. The article makes recommendations on those factors influencing the design of the software and for its optimal use in practice

  16. Large power supply facilities for fusion research

    International Nuclear Information System (INIS)

    Miyahara, Akira; Yamamoto, Mitsuyoshi.

    1976-01-01

    The authors had opportunities to manufacture and to operate two power supply facilities, that is, 125MVA computer controlled AC generator with a fly wheel for JIPP-T-2 stellerator in Institute of Plasma Physics, Nagoya University and 3MW trial superconductive homopolar DC generator to the Japan Society for Promotion of Machine Industry. The 125MVA fly-wheel generator can feed both 60MW (6kV x 10kA) DC power for toroidal coils and 20MW (0.5kV x 40kA) DC power for helical coils. The characteristic features are possibility of Bung-Bung control based on Pontrjagin's maximum principle, constant current control or constant voltage control for load coils, and cpu control for routine operation. The 3MW (150V-20000A) homopolar generator is the largest in the world as superconductive one, however, this capacity is not enough for nuclear fusion research. The problems of power supply facilities for large Tokamak devices are discussed

  17. Brayton Isotope Power System (BIPS) facility specification

    International Nuclear Information System (INIS)

    1976-01-01

    General requirements for the Brayton Isotope Power System (BIPS)/Ground Demonstration System (GDS) assembly and test facility are defined. The facility will include provisions for a complete test laboratory for GDS checkout, performance, and endurance testing, and a contamination-controlled area for assembly, fabrication, storage, and storage preparation of GDS components. Specifications, schedules, and drawings are included

  18. Brayton Isotope Power System (BIPS) facility specification

    Energy Technology Data Exchange (ETDEWEB)

    1976-05-31

    General requirements for the Brayton Isotope Power System (BIPS)/Ground Demonstration System (GDS) assembly and test facility are defined. The facility will include provisions for a complete test laboratory for GDS checkout, performance, and endurance testing, and a contamination-controlled area for assembly, fabrication, storage, and storage preparation of GDS components. Specifications, schedules, and drawings are included.

  19. HTS power lead testing at the Fermilab magnet test facility

    Energy Technology Data Exchange (ETDEWEB)

    Rabehl, R.; Carcagno, R.; Feher, S.; Huang, Y.; Orris, D.; Pischalnikov, Y.; Sylvester, C.; Tartaglia, M.; /Fermilab

    2005-08-01

    The Fermilab Magnet Test Facility has tested high-temperature superconductor (HTS) power leads for cryogenic feed boxes to be placed at the Large Hadron Collider (LHC) interaction regions and at the new BTeV C0 interaction region of the Fermilab Tevatron. A new test facility was designed and operated, successfully testing 20 pairs of HTS power leads for the LHC and 2 pairs of HTS power leads for the BTeV experiment. This paper describes the design and operation of the cryogenics, process controls, data acquisition, and quench management systems. Results from the facility commissioning are included, as is the performance of a new insulation method to prevent frost accumulation on the warm ends of the power leads.

  20. HTS power lead testing at the Fermilab magnet test facility

    International Nuclear Information System (INIS)

    Rabehl, R.; Carcagno, R.; Feher, S.; Huang, Y.; Orris, D.; Pischalnikov, Y.; Sylvester, C.; Tartaglia, M.

    2005-01-01

    The Fermilab Magnet Test Facility has tested high-temperature superconductor (HTS) power leads for cryogenic feed boxes to be placed at the Large Hadron Collider (LHC) interaction regions and at the new BTeV CO interaction region of the Fermilab Tevatron. A new test facility was designed and operated, successfully testing 20 pairs of HTS power leads for the LHC and 2 pairs of HTS power leads for the BTeV experiment. This paper describes the design and operation of the cryogenics, process controls, data acquisition, and quench management systems. Results from the facility commissioning are included, as is the performance of a new insulation method to prevent frost accumulation on the warm ends of the power leads

  1. Capabilities of the Power Burst Facility

    International Nuclear Information System (INIS)

    Spencer, W.A.; Jensen, A.M.; McCardell, R.K.

    1982-01-01

    The unique and diverse test capabilities of the Power Burst Facility (PBF) are described in this paper. The PBF test reactor, located at the Idaho National Engineering Laboratory, simulates normal, off-normal, and accident operating conditions of light water reactor fuel rods. An overview description is given, with specific detail on design and operating characteristics of the driver core, experiment test loop, fission product detection system, test train assembly facility, and support equipment which make the testing capability of the PBF so versatile

  2. No nuclear power. No disposal facility?

    Energy Technology Data Exchange (ETDEWEB)

    Feinhals, J. [DMT GmbH und Co.KG, Hamburg (Germany)

    2016-07-01

    Countries with a nuclear power programme are making strong efforts to guarantee the safe disposal of radioactive waste. The solutions in those countries are large disposal facilities near surface or in deep geological layers depending on the activity and half-life of the nuclides in the waste. But what will happen with the radioactive waste in countries that do not have NPPs but have only low amounts of radioactive waste from medical, industrial and research facilities as well as from research reactors? Countries producing only low amounts of radioactive waste need convincing solutions for the safe and affordable disposal of their radioactive waste. As they do not have a fund by an operator of nuclear power plants, those countries need an appropriate and commensurate solution for the disposal of their waste. In a first overview five solutions seem to be appropriate: (i) the development of multinational disposal facilities by using the existing international knowhow; (ii) common disposal with hazardous waste; (iii) permanent storage; (iv) use of an existing mine or tunnel; (v) extension of the borehole disposal concept for all the categories of radioactive wastes.

  3. Development of the power ramping facility at JMTR

    International Nuclear Information System (INIS)

    Nakata, Hirokatsu; Sezaki, Katsuji; Nakazaki, Chosaburo; Ishii, Tadahiko; Ito, Haruhiko; Abe, Hiroshi

    1985-03-01

    The LWR fuel power ramping facility have been being developed at JMTR since 1978. This report, following previous reports, JAERI-M 8533 and 9343, summarizes the results of performance test performed in 1981 on the 3 He power controlled boiling water capsule, which is a basic part of the facility. Various measurements were carried out during reactor operation on each part of the capsule, i.e. capsule itself, capsule control unit and 3 He power control unit, after a long-time cold run test of the units. Through the test, it was confirmed that the capsule satisfies the specifications which stated that LWR fuel pin should be power-ramped under BWR conditions up to 50 kW/m with a change factor of more than 2, and that the control units operate in a good condition. (author)

  4. The enforcement order for the law for arrangement of surrounding areas of power generating facilities

    International Nuclear Information System (INIS)

    1980-01-01

    This rule is established under the provisions of the law for the redevelopment of the surrounding areas of power generating facilities. Persons who install power generating facilities under the law include general electric power enterprises and wholesale electric power enterprises defined under the electric enterprises act and the Power Reactor and Nuclear Fuel Development Corporation. The scale of these facilities defined under the law is 350,000 kilo-watts output for atomic and thermal power generating facilities, 10,000 kilo-watts output for the facilities utilizing geothermal energy, 100,000 kilo-watts output for facilities whose main fuel is coal, and 1,000 kilo-watts output for hydraulic power generating facilities, etc. The facilities closely related to atomic power generation include the reprocessing and examination facilities of fuel materials spent in atomic power reactors, the reactors installed by the Japan Atomic Energy Research Institute for studying on the safety of atomic power reactors, the experimental fast reactors and the uranium enrichment facilities established by the Power Reactor and Nuclear Fuel Development Corporation. The public facilities in this rule are those for communication, sport and recreation, environment hygiene, education and culture, medicine, social welfare, fire fighting, etc. Governors of prefectures who intend to get approval under the law shall file redevelopment plans to the competent minister through the Minister of the International Trade and Industry. (Okada, K.)

  5. EPA Facility Registry Service (FRS): Power Plants

    Data.gov (United States)

    U.S. Environmental Protection Agency — This GIS dataset contains data on power plants, based on the Energy Information Administration's EIA-860 dataset and supplemented with data from EPA's Facility...

  6. Development of the Ukrainian power sector taking into account the environmental impact of power facilities

    International Nuclear Information System (INIS)

    Dyakova, E.; Krymskaya, L.

    1997-01-01

    This paper concentrates on the following problems: Evaluation of total environmental impacts from all kinds of power plants on the whole territory of Ukraine; evaluation of environmental impacts in selected regions due to uneven power facilities distribution. Analysis of the environmental situation in Ukraine was conducted using the IMPACTS module of the ENPEP package with account to the Ukrainian energy requirements in perspective. Some recommendations concerning the development of power facilities and reduction of air emissions are also given. (author). 7 figs, 5 tabs

  7. Development of the Ukrainian power sector taking into account the environmental impact of power facilities

    Energy Technology Data Exchange (ETDEWEB)

    Dyakova, E; Krymskaya, L [Institute for Nuclear Research, National Academy of Science, Kiev (Ukraine)

    1997-09-01

    This paper concentrates on the following problems: Evaluation of total environmental impacts from all kinds of power plants on the whole territory of Ukraine; evaluation of environmental impacts in selected regions due to uneven power facilities distribution. Analysis of the environmental situation in Ukraine was conducted using the IMPACTS module of the ENPEP package with account to the Ukrainian energy requirements in perspective. Some recommendations concerning the development of power facilities and reduction of air emissions are also given. (author). 7 figs, 5 tabs.

  8. Distributed Supply Coordination for Power-to-Gas Facilities Embedded in Energy Grids

    NARCIS (Netherlands)

    Alkano, Desti; Scherpen, Jacquelien M. A.

    This paper considers hydrogen and renewable electricity from power-to-gas (PtG) facilities supplied to a gas grid, a mobility sector, and a power grid. The PtG facilities are equipped with hydrogen buffers and fuel cells. The goal is to maximize the expected profit of PtG facilities without

  9. The regulation for delivery of subsidies for measures of promoting power source location for nuclear power generating facilities

    International Nuclear Information System (INIS)

    1977-01-01

    The Regulation is based on the prescriptions of the Enforcement Order for the Law for Arrangement of Surrounding Areas of Power Generating Facilities, the Law for Proper Budget Enforcement Concerning Subsidies and its Enforcement Order. These rules apply to the subsidies concerning nuclear power generating facilities, reprocessing facilities and test and examination facilities for nuclear fuel materials used for power generating reactors, reactors used for research on the safety of power generating reactors, and experimental reactors for fast breeder reactors. The limits of subsidies are specified respectively for the cases that a unit of power generating facility or two and more units of such facilities are set up in a local municipality. The subsidies are delivered for the expenses occurred in the period, beginning from the fiscal year when construction of the generating facility concerned starts or the arrangement plan of the concerned project is approved, and ending in the fiscal year when such construction comes to an end. The subsidies are given as evenly as possible in each fiscal year. The applicants of the subsidies file the applications attached with the explanations of the projects to the chief of the competent ministry (Director General of the Science and Technology Agency or the Minister of International Trade and Industry). Terms of delivery, reports submitted by the receivers of the subsidies and other related matters are specified. (Okada, K.)

  10. Post 9-11 Security Issues for Non-Power Reactor Facilities

    International Nuclear Information System (INIS)

    Zaffuts, P. J.

    2003-01-01

    This paper addresses the legal and practical issues arising out of the design and implementation of a security-enhancement program for non power reactor nuclear facilities. The security enhancements discussed are derived from the commercial nuclear power industry's approach to security. The nuclear power industry's long and successful experience with protecting highly sensitive assets provides a wealth of information and lessons that should be examined by other industries contemplating security improvements, including, but not limited to facilities using or disposing of nuclear materials. This paper describes the nuclear industry's approach to security, the advantages and disadvantages of its constituent elements, and the legal issues that facilities will need to address when adopting some or all of these elements in the absence of statutory or regulatory requirements to do so

  11. Post 9-11 Security Issues for Non-Power Reactor Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Zaffuts, P. J.

    2003-02-25

    This paper addresses the legal and practical issues arising out of the design and implementation of a security-enhancement program for non power reactor nuclear facilities. The security enhancements discussed are derived from the commercial nuclear power industry's approach to security. The nuclear power industry's long and successful experience with protecting highly sensitive assets provides a wealth of information and lessons that should be examined by other industries contemplating security improvements, including, but not limited to facilities using or disposing of nuclear materials. This paper describes the nuclear industry's approach to security, the advantages and disadvantages of its constituent elements, and the legal issues that facilities will need to address when adopting some or all of these elements in the absence of statutory or regulatory requirements to do so.

  12. Ministry of ordinance determining the technical standard concerning atomic energy facilities for power generation

    International Nuclear Information System (INIS)

    1985-01-01

    The ministerial ordinance provides for the technical standards for the power generation of nuclear facilities; i.e., electric power facilities generating electricity with nuclear energy for motive power, according to the Electricity Enterprises Act. The contents are as follows: protection against fires, aseismatic design, radiation protective barriers, structural protection for sitings, reactor installation, safety measures, materials and structures, safety valves, pressure resistance tests, reactor core, radiation shields, reactor cooling, emergency core cooling system, facility equipment, alarm system, reactor control system, reactor control room, fuel storage facility, fuel handling facility, ventilation equipment, radioactive contamination prevention, radioactive waste management facility, reactor containment facility, and so on. (Kubozono, M.)

  13. Maximization of revenues for power sales from a solid waste resources recovery facility

    Energy Technology Data Exchange (ETDEWEB)

    1991-12-01

    The report discusses the actual implementation of the best alternative in selling electrical power generated by an existing waste-to-energy facility, the Metro-Dade County Resources Recovery Plant. After the plant processes and extracts various products out of the municipal solid waste, it burns it to produce electrical power. The price for buying power to satisfy the internal needs of our Resources Recovery Facility (RRF) is substantially higher than the power price for selling electricity to any other entity. Therefore, without any further analysis, it was decided to first satisfy those internal needs and then export the excess power. Various alternatives were thoroughly explored as to what to do with the excess power. Selling power to the power utilities or utilizing the power in other facilities were the primary options.

  14. The enforcement order for the law for arrangement of surrounding areas of power generating facilities

    International Nuclear Information System (INIS)

    1977-01-01

    The Order is based on the prescriptions of the Law for the Arrangement of Surrounding Areas of Power Generating Facilities. Those establishing power generating facilities are general and wholesale electric enterprisers provided for by the Electricity Enterprises Act as well as the Power Reactor and Nuclear Fuel Development Corporation. The generating capacity is specified as 350,000 kilowatts for nuclear and steam power generating facilities, 150,000 kilowatts for those set up by the Corporation, 100,000 kilowatts for those using coal as main fuel, and 10,000 kilowatts for water power generation and geothermal plants. The facilities closely connected to nuclear power generation include the reprocessing facilities and test and examination facilities for nuclear fuel materials used for power-generating nuclear reactors, reactors used for the research on the safety of power generating reactors, and experimental reactors for fast breeder reactors. The public facilities consist of communication facilities, and the facilities for sports and recreations, environmental hygiene, education and culture, medicine, social welfare, fire fighting, etc. Prefectural governors ought to file the arrangement plans to the competent minister through the Minister of International Trade and Industry to get the permission prescribed by the Law. The subsidy is not granted to the expenses of the enterprises undertaken by the nation or those enterprises, a part of the expenses of which is borne or subsidized by the nation. (Okada, K.)

  15. Yearly program of safety research in nuclear power facilities from fiscal 1981 to 1985

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    Nuclear safety research plans for nuclear power facilities and others from fiscal 1981 to 1985 are presented for the following areas: the safety of LWR fuel, loss-of-coolant accidents, the structural safety of LWR installations, the reduction of radioactive material release from nuclear power facilities, the stochastic safety evaluation of nuclear power facilities, the aseismicity of nuclear power facilities, the safety of nuclear fuel facilities, and the safety of nuclear fuel transport vessels. In the respective areas, the needs for research and the outline of research works are summarized. Then, about the major research works in each area, the purpose, contents, term and responsible institution of the research are given. (Mori, K.)

  16. Power conditioning development for the National Ignition Facility

    International Nuclear Information System (INIS)

    Newton, M.A.; Larson, D.W.; Wilson, J.M.; Harjes, H.C.; Savage, M.E.; Anderson, R.L.

    1996-10-01

    The National Ignition Facility (NIF) is a high energy glass laser system and target chamber that will be used for research in inertial confinement fusion. The 192 beams of the NIF laser system are pumped by over 8600 Xenon flashlamps. The power conditioning system for NIF must deliver nearly 300 MJ of energy to the flashlamps in a cost effective and reliable manner. The present system design has over 200 capacitive energy storage modules that store approximately 1.7 MJ each and deliver that energy through a single switch assembly to 20 parallel sets of two series flashlamps. Although there are many possible system designs, few will meet the aggressive cost goals necessary to make the system affordable. Sandia National Laboratory (SNL) and Lawrence Livermore National Laboratory (LLNL) are developing the system and component technologies that will be required to build the power conditioning system for the National Ignition Facility. This paper will describe the ongoing development activities for the NIF power conditioning system

  17. Micro-Combined Heat and Power Device Test Facility

    Data.gov (United States)

    Federal Laboratory Consortium — NIST has developed a test facility for micro-combined heat and power (micro-CHP) devices to measure their performance over a range of different operating strategies...

  18. Power conditioning for the National Ignition Facility

    International Nuclear Information System (INIS)

    Larson, D.W.; Anderson, R.; Boyes, J.

    1994-01-01

    A cost-effective, 320-MJ power-conditioning system has been completed for the proposed National Ignition Facility (NIF). The design features include metallized dielectric capacitors, a simple topology, and large (1.6-MJ) module size. Experimental results address the technical risks associated with the design

  19. A multi-tank storage facility to effect power control in the PBMR power cycle

    International Nuclear Information System (INIS)

    Matimba, T.A.D.; Krueger, D.L.W.; Mathews, E.H.

    2007-01-01

    This article presents the concept of a storage facility used to effect power control in South Africa's PBMR power cycle. The concept features a multiple number of storage vessels whose purpose is to contain the working medium, helium, as it is withdrawn from the PBMR's closed loop power cycle, at low energy demand. This helium is appropriately replenished to the power cycle as the energy demand increases. Helium mass transfer between the power cycle and the storage facility, henceforth known as the inventory control system (ICS), is carried out by way of the pressure differential that exists between these two systems. In presenting the ICS concept, emphasis is placed on storage effectiveness; hence the discussion in this paper is centred on those features which accentuate storage effectiveness, namely:- Storage vessel multiplicity; - Unique initial pressures for each vessel arranged in a cascaded manner; and - A heat sink placed in each vessel to provide thermal inertia. Having presented the concept, the objective is to qualitatively justify the presence of each of the above-mentioned features using thermodynamics as a basis

  20. ACIGA's high optical power test facility

    Energy Technology Data Exchange (ETDEWEB)

    Ju, L [School of Physics, University of Western Australia, Perth (Australia); Aoun, M [Computer and Information Science, Edith Cowan University, Perth (Australia); Barriga, P [School of Physics, University of Western Australia, Perth (Australia)] [and others

    2004-03-07

    Advanced laser interferometer detectors utilizing more than 100 W of laser power and with {approx}10{sup 6} W circulating laser power present many technological problems. The Australian Consortium for Interferometric Gravitational Astronomy (ACIGA) is developing a high power research facility in Gingin, north of Perth, Western Australia, which will test techniques for the next generation interferometers. In particular it will test thermal lensing compensation and control strategies for optical cavities in which optical spring effects and parametric instabilities may present major difficulties.

  1. Decommissioning of nuclear power facilities

    International Nuclear Information System (INIS)

    Nosovskij, A.V.; Vasil'chenko, V.N.; Klyuchnikov, A.A.; Yashchenko, Ya.V.

    2005-01-01

    This is the first manual in Ukraine giving the complete review of the decommissioning process of the nuclear power facilities including the issues of the planning, design documentation development, advanced technology description. On the base of the international and domestic experience, the issues on the radwaste management, the decontamination methods, the equipment dismantling, the remote technology application, and also the costs estimate at decommissioning are considered. The special attention to the personnel safety provision, population and environment at decommissioning process is paid

  2. Human engineering considerations in the design of New Virginia Power Radwaste facilities

    International Nuclear Information System (INIS)

    Bankley, A.V.; Morris, L.L.; Lippard, D.W.

    1988-01-01

    Human engineering principles were considered by Virginia Power in the recent design of new radwaste facilities (NRFs) for both the Surry and North Anna power stations. Virginia Power recognized that the rigorous application of human engineering principles to the NRF design was essential to the ultimate success or failure of the facilities. Success of the NRF should not only be measured in the volume of radwaste processed but also by other factors such as (a) availability and maintainability of preferred equipment, (b) as-low-as-reasonably-achievable considerations, (c) actual release rates versus achievable release rates, and (d) flexibility to deal with varying circumstances. Each of these success criteria would suffer as the result of operator/human inefficiencies or error. Therefore, human engineering should be applied to the maximum practical extent to minimize such inefficiencies or errors. No method is ever going to ensure a perfectly human-engineered facility design. Virginia Power believes, however, that significant strides have been made in efforts to design and construct a successful radwaste processing facility, a facility where operating success rests with the ability of the human operators to perform their jobs in an efficient and reliable fashion

  3. Technology developments for ACIGA high power test facility for advanced interferometry

    Energy Technology Data Exchange (ETDEWEB)

    Barriga, P [School of Physics, University of Western Australia, Perth, WA 6009 (Australia); Barton, M [California Institute of Technology, LIGO Project, Pasadena, CA 91125 (United States); Blair, D G [School of Physics, University of Western Australia, Perth, WA 6009 (Australia)] [and others

    2005-05-21

    The High Optical Power Test Facility for Advanced Interferometry has been built by the Australian Consortium for Interferometric Gravitational Astronomy north of Perth in Western Australia. An 80 m suspended cavity has been prepared in collaboration with LIGO, where a set of experiments to test suspension control and thermal compensation will soon take place. Future experiments will investigate radiation pressure instabilities and optical spring effects in a high power optical cavity with {approx}200 kW circulating power. The facility combines research and development undertaken by all consortium members, whose latest results are presented.

  4. Technology developments for ACIGA high power test facility for advanced interferometry

    International Nuclear Information System (INIS)

    Barriga, P; Barton, M; Blair, D G

    2005-01-01

    The High Optical Power Test Facility for Advanced Interferometry has been built by the Australian Consortium for Interferometric Gravitational Astronomy north of Perth in Western Australia. An 80 m suspended cavity has been prepared in collaboration with LIGO, where a set of experiments to test suspension control and thermal compensation will soon take place. Future experiments will investigate radiation pressure instabilities and optical spring effects in a high power optical cavity with ∼200 kW circulating power. The facility combines research and development undertaken by all consortium members, whose latest results are presented

  5. Management of the high-level nuclear power facilities

    International Nuclear Information System (INIS)

    Preda, Marin

    2003-05-01

    This thesis approaches current issues in the management of the high power nuclear facilities and as such it appears to be important particularly for nuclear power plant operation topics. Of special interest are the failure events entailing possible catastrophic situations. The contents is structured onto ten chapters. The first chapter describes the operation regimes of the nuclear high power facilities. Highlighted here are the thesis scope and the original features of the work. The second chapter deals with operational policies developed in order to ensure the preventive maintenance of the nuclear installations. Also managing structures are described devoted to practical warranting the equipment safety function of non-classical power stations. In the third chapter cases of nuclear accidents are analyzed especially stressing the probabilistic risk and the operation regimes having in view the elimination of catastrophic events. In the fourth and fifth chapters the control of nuclear radiation emission is treated focusing the quality issue of nuclear installations required to avoid hazardous effects at level of nuclear reactor operation stage. At the same time set of operational measures is given here for preventing risks, catastrophes and chaotic situations. The chapter five presents both theoretical and practical approaches of the nuclear reactor core management concerning particularly the fuel testing, the water primary system and the quality of the involved equipment. In the sixth and seventh chapters issues of risk-quality correlations are approached as well as the structure of expert systems for monitoring the operational regimes of nuclear facilities. The efficiency of the power systems with nuclear injection is discussed and some original ideas developed in this work are evidenced in the eighth and ninth chapters. Presented are here both the operational principles and models of raising the efficiency of the interconnected nuclear stations and prices' policy

  6. The December 7, 1988 Armenia earthquake effects on selected power, industrial and commercial facilities

    International Nuclear Information System (INIS)

    Campbell, R.D.; Griffin, M.J.; Bragagnolo, L.J.; Yanev, P.I.

    1996-01-01

    A detailed overview of the Armenia earthquake (occurred on December 7, 1988) effects on selected power, industrial and commercial facilities is presented in this paper. It involves geologic and seismology study of the region; description of the design building standards; detailed description of the damaged nuclear and other power plants as well as other industrial facilities. Extensive damage was sustained by the industrial facilities in the epicentral area, the majority due to poor design and construction. The effects on power facilities were much less severe. response time to restore power to the transmission was 2 to 3 days following the earthquake. Power plant equipment without rigorous seismic design performed well. Mechanical equipment, pumps, valves, compressors, and piping all performed with minimal damage, Electrical control equipment if properly anchored performed well without exception

  7. Synthetic methods for beam to beam power balancing capability of large laser facilities

    International Nuclear Information System (INIS)

    Chen Guangyu; Zhang Xiaomin; Zhao Runchang; Zheng Wanguo; Yang Xiaoyu; You Yong; Wang Chengcheng; Shao Yunfei

    2011-01-01

    To account for output power balancing capability of large laser facilities, a synthetic method with beam to beam root-mean-square is presented. Firstly, a conversion process for the facilities from original data of beam powers to regular data is given. The regular data contribute to the normal distribution approximately, and then a corresponding simple method of root-mean-square for beam to beam power balancing capability is given.Secondly, based on theory of total control charts and cause-selecting control charts, control charts with root-mean-square are established which show short-term variety of power balancing capability of the facilities. Mean rate of failure occurrence is also defined and used to describe long-term trend of global balancing capabilities of the facilities. Finally, advantages of the intuitive and efficient diagnosis for synthetic methods are illustrated by analysis of experimental data. (authors)

  8. Emergency response facility technical data system of Taiwan Power Company

    International Nuclear Information System (INIS)

    Lin, E.; Liang, T.M.

    1987-01-01

    Taiwan Power Company (Taipower) has developed its emergency response facility program since 1981. This program is integrated with the following activities to enhance the emergency response capability of nuclear power plants: (1) survey of the plant instrumentation based on the requirements of R.G. 1.97; (2) improvement of plant specific emergency operating procedures based on the emergency response guidelines developed by the Owners group; (3) implementation of the detailed control room design review with the consideration of human engineering and task analysis; and (4) organization, staff and communication of emergency planning of nuclear power plant. The emergency response facility programs of Taipower are implemented in Chinshan (GE BWR4/MARK I), Kuosheng (GE BWR6/MARK III) and Maanshan (W PWR). The major items included in each program are: (1) to establish new buildings for On-Site Technical Support Center, Near-Site Emergency Operation Facility; (2) to establish an Emergency Executive Center at Taipower headquarters; (3) to establish the communication network between control room and emergency response facilities; and (4) to install a dedicated Emergency Response Facility Technical Data System (ERFTDS) for each plant. The ERFTDS provides the functions of data acquisition, data processing, data storage and display in meeting with the requirements of NUREG 0696. The ERFTDS is designed with plant specific requirements. These specific requirements are expected to be useful not only for the emergency condition but also for normal operation conditions

  9. The enforcement order for the law for arrangement of surrounding areas of power generating facilities

    International Nuclear Information System (INIS)

    1979-01-01

    The order is defined under the law for arrangement of surrounding areas of power generating facilities. Establishers of power generating facilities shall be hereunder general electric enterprisers, wholesale electric enterprisers and the Power Reactor and Nuclear Fuel Development Corporation. The scale of power generating facilities provided by the order is 350,000 kilo-watts for atomic and steam power generation and 5,000 kilo-watts for hydroelectric power. Equipment closely related to atomic power generation shall include facilities for reprocessing and examination of nuclear fuel materials spent for power generating reactors, reactors used for research of the safety of power generating reactors, experimental fast breeding reactors and experimental uranium enrichment facilities. Requisites for the extent of industrial accumulation are that the area belongs to those self-governing bodies whose industrial accumulation is more than the 8th degree. Public facilities specified are those for communication, sports or recreation, environmental hygiene, education and culture, medicine, social welfare, fire fighting and heat supplying, etc. Governors of the prefectures shall file arrangement programs to the Minister in charge through the Minister of International Trade and Industry to get the permission stipulated by the law. Subsidies shall not be paid to those enterprises which are executed by the government or a part of the expenses is born or supported by it. (Okada, K.)

  10. Low-power critical facilities: their role in the nuclear renaissance

    International Nuclear Information System (INIS)

    Didsbury, R.

    2011-01-01

    This paper discusses the role of low power critical facilities and their role in the nuclear renaissance. It outline the role of human capital in some detail. sufficient conditions for the renaissance are that nuclear power is safe, sustainable, economical and proliferation resistant.

  11. Base isolation for nuclear power and nuclear material facilities

    International Nuclear Information System (INIS)

    Eidinger, J.M.; Kircher, C.A.; Vaidya, N.; Constantinou, M.; Kelly, J.M.; Seidensticker, R.; Tajirian, F.F.; Ovadia, D.

    1989-01-01

    This report serves to document the status of the practice for the use of base isolation systems in the design and construction of nuclear power and nuclear material facilities. The report first describes past and current (1989) applications of base isolation in nuclear facilities. The report then provides a brief discussion of non-nuclear applications. Finally, the report summarizes the status of known base-isolation codes and standards

  12. Economic benefits of power factor correction at a nuclear facility

    International Nuclear Information System (INIS)

    Boger, R.M.; Dalos, W.; Juguilon, M.E.

    1986-01-01

    The economic benefits of correcting poor power factor at an operating nuclear facility are shown. A project approach for achieving rapid return of investment without disrupting plant availability is described. Examples of technical problems associated with using capacitors for power factor correction are presented

  13. Mortality monitoring design for utility-scale solar power facilities

    Science.gov (United States)

    Huso, Manuela; Dietsch, Thomas; Nicolai, Chris

    2016-05-27

    IntroductionSolar power represents an important and rapidly expanding component of the renewable energy portfolio of the United States (Lovich and Ennen, 2011; Hernandez and others, 2014). Understanding the impacts of renewable energy development on wildlife is a priority for the U.S. Fish and Wildlife Service (FWS) in compliance with Department of Interior Order No. 3285 (U.S. Department of the Interior, 2009) to “develop best management practices for renewable energy and transmission projects on the public lands to ensure the most environmentally responsible development and delivery of renewable energy.” Recent studies examining effects of renewable energy development on mortality of migratory birds have primarily focused on wind energy (California Energy Commission and California Department of Fish and Game, 2007), and in 2012 the FWS published guidance for addressing wildlife conservation concerns at all stages of land-based wind energy development (U.S. Fish and Wildlife Service, 2012). As yet, no similar guidelines exist for solar development, and no published studies have directly addressed the methodology needed to accurately estimate mortality of birds and bats at solar facilities. In the absence of such guidelines, ad hoc methodologies applied to solar energy projects may lead to estimates of wildlife mortality rates that are insufficiently accurate and precise to meaningfully inform conversations regarding unintended consequences of this energy source and management decisions to mitigate impacts. Although significant advances in monitoring protocols for wind facilities have been made in recent years, there remains a need to provide consistent guidance and study design to quantify mortality of bats, and resident and migrating birds at solar power facilities (Walston and others, 2015).In this document, we suggest methods for mortality monitoring at solar facilities that are based on current methods used at wind power facilities but adapted for the

  14. Lawrence Berkeley laboratory neutral-beam engineering test facility power-supply system

    International Nuclear Information System (INIS)

    Lutz, I.C.; Arthur, C.A.; deVries, G.J.; Owren, H.M.

    1981-10-01

    The Lawrence Berkeley Laboratory is upgrading the neutral beam source test facility (NBSTF) into a neutral beam engineering test facility (NBETF) with increased capabilities for the development of neutral beam systems. The NBETF will have an accel power supply capable of 170 kV, 70 A, 30 sec pulse length, 10% duty cycle; and the auxiliary power supplies required for the sources. This paper describes the major components, their ratings and capabilities, and the flexibility designed to accomodate the needs of source development

  15. Power Systems Development Facility. Quarterly report, July--September 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    The objective of this project is to evaluate hot gas particle control technologies using coal-derived gas streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particulate control device issues to be addressed include the integration of the particulate control devices into coal utilization systems, on-line cleaning techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a fimction of particle size, and scale-up of particulate control systems to commercial size. The conceptual design of the facility was extended to include a within scope, phased expansion of the existing Hot Gas Cleanup Test Facility Cooperative Agreement to also address systems integration issues of hot particulate removal in advanced coal-based power generation systems. This expansion included the consideration of the following modules at the test facility in addition to the original Transport Reactor gas source and hot gas cleanup units: carbonizer/pressurized circulating fluidized bed gas source; hot gas cleanup units to mate to all gas streams; combustion gas turbine; and fuel cell and associated gas treatment. This expansion to the Hot Gas Cleanup Test Facility is herein referred to as the Power Systems Development Facility (PSDF). The major emphasis during this reporting period was continuing the detailed design of the facility towards completion and integrating the balance-of-plant processes and particulate control devices (PCDS) into the structural and process designs. Substantial progress in construction activities was achieved during the quarter. Delivery and construction of the process structural steel is nearing completion. Nearly all equipment are set in its place and the FW equipment and the PCDs are being set in the structure.

  16. S-band 45 MW peak power test facility at RRCAT

    International Nuclear Information System (INIS)

    Wanmode, A. Yashwant; Reddy, Sivananda; Mulchandani, J.; Mohania, Praveen; Shrivastava, B. Purushottam

    2015-01-01

    RRCAT is engaged in the design and development of high energy electron LINAC as future injectors for the Booster Synchrotron for Indus-1 and Indus-2 SRS. The high energy LINAC will need microwave power over 30 MW depending on the number of structures to be energized. In order to have advance preparations for this development a 45 MW S-Band test facility has been designed and developed at RRCAT. The test stand is built around a 45 MW peak power S-band pulsed klystron, A conventional pulse forming network based modulator for klystron has been designed and developed. The WR-284 waveguide transmission system consisting of dual directional couplers, SF 6 gas pressurization unit, high power waveguide load and arc sensor has been developed and interfaced with the klystron. The klystron has been successfully tested up to 30 MW peak power at 2856 MHz on SF 6 pressurized waveguide line. A solid state S Band driver amplifier up to 1 kW output power was designed developed for driving the klystron. This paper describes the results of 30 MW peak power test of this facility. (author)

  17. Power Reactor Thoria Reprocessing Facility (PRTRF), Trombay

    International Nuclear Information System (INIS)

    Dhami, P.S; Yadav, J.S; Agarwal, K.

    2017-01-01

    Exploitation of the abundant thorium resources to meet sustained energy demand forms the basis of the Indian nuclear energy programme. To gain reprocessing experience in thorium fuel cycle, thoria was irradiated in research reactor CIRUS in early sixties. Later in eighties, thoria bundles were used for initial flux flattening in some of the pressurized heavy water reactors (PHWRs). The research reactor irradiated thoria contained small content (∼ 2-3ppm) of "2"3"2U in "2"3"3U product, which did not pose any significant radiological problems during processing in Uranium Thorium Separation Facility (UTSF), Trombay. Thoria irradiated in PHWRs on discharge contained (∼ 0.5-1.5% "2"3"3U with significant "2"3"2U content (100-500 ppm) requiring special radiological attention. Based on the experience from UTSF, a new facility viz. Power Reactor Thoria Reprocessing Facility (PRTRF), Trombay was built which was hot commissioned in the year 2015

  18. Occupational radiation exposure at commercial nuclear power reactors and other facilities, 1989

    International Nuclear Information System (INIS)

    Raddatz, C.T.

    1992-04-01

    This report summarizes the occupational radiation exposure information that has been reported to the NRC's Radiation Exposure Information Reporting System (REIRS) by nuclear power facilities and certain other categories of NRC 1 licensees during the years 1969 through 1989. The bulk of the data presented in the report was obtained from annual radiation exposure reports submitted in accordance with the requirements of 10 CFR 20.407 and the technical specifications of nuclear power plants. Data on workers terminating their employment at certain NRC 1 licensed facilities were obtained from reports submitted pursuant to 10 CFR 20.408. The 1989 annual reports submitted by about 448 licensees indicated that approximately 216,294 individuals were monitored 111,000 of whom were monitored by nuclear power facilities. They incurred an average individual does of 0.18 rem (cSv) and an average measurable dose of 0.36 (cSv). Termination radiation exposure reports were analyzed to reveal that about 113,535 individuals completed their employment with one or more of the 448 covered licensees during 1989. Some 76,561 of these individuals terminated from power reactor facilities, and about 10, 344 of them were considered to be transient workers who received an average dose of 0.64 rem (cSv)

  19. Occupational radiation exposure at commercial nuclear power reactors and other facilities, 1988

    International Nuclear Information System (INIS)

    Raddatz, C.T.

    1991-07-01

    This report summarizes the occupational radiation exposure information that has been reported to the NRC's Radiation Exposure Information Reporting System (REIRS) by nuclear power facilities and certain other categories of NRC licensees during the years 1969 through 1988. The bulk of the data presented in the report was obtained from annual radiation exposure reports submitted in accordance with the requirements of 10 CFR 20.407 and the technical specifications of nuclear power plants. Data on workers terminating their employment at certain NRC licensed facilities were obtained from reports submitted pursuant to 10 CFR 20.408. The 1988 annual reports submitted by about 429 licensees indicated that approximately 220,048 individuals were monitored, 113,00 of whom were monitored by nuclear power facilities. They incurred an average individual dose of 0.20 rem (cSv) and an average measurable dose of 0.41 (cSv). Termination radiation exposure reports were analyzed to reveal that about 113,072 individuals completed their employment with one or more of the 429 covered licensees during 1988. Some 80,211 of these individuals terminated from power reactor facilities, and about 8,760 of them were considered to be transient workers who received an average dose of 0.27 rem (cSv). 17 refs., 11 figs., 29 tabs

  20. Occupational radiation exposure at commercial nuclear power reactors and other facilities, 1991

    International Nuclear Information System (INIS)

    Raddatz, C.T.

    1993-07-01

    This report summarizes the occupational radiation exposure information that has been reported to the NRC's Radiation Exposure Information Reporting System (REIRS) by nuclear power facilities and certain other categories of NRC licensees during the years 1969 through 1991. The bulk of the data presented in the report was obtained from annual radiation exposure reports submitted in accordance with the requirements of 10 CFR 20.407 and the technical specifications of nuclear power plants. Data on workers terminating their employment at certain NRC licensed facilities were obtained from reports submitted pursuant to 10 CFR 20.408. The 1991 annual reports submitted by about 436 licensees indicated that approximately 206,732 individuals were monitored, 182,334 of whom were monitored by nuclear power facilities. They incurred an average individual dose of 0.15 rem (cSv) and an average measurable dose of about 0.31 (cSv). Termination radiation exposure reports were analyzed to reveal that about 96,231 individuals completed their employment with one or more of the 436 covered licensees during 1991. Some 68,115 of these individuals terminated from power reactor facilities, and about 7,763 of them were considered to be transient workers who received an average dose of 0.52 rem (cSv)

  1. Training of nuclear power facility personnel. Part 1

    International Nuclear Information System (INIS)

    1989-06-01

    The proceedings of the conference entitled ''Training of Nuclear Power Facility Personnel'' and held in Tale, Czechoslovakia, on 24 - 27 April 1989, contain full texts of 58 contributions, 57 of which fall in the INIS subject scope. The aim of the conference was to summarize experience gained during the training and education of Czechoslovak nuclear power plants operating personnel, to put forth new suggestions for increasing the safety and reliability of nuclear power plants, and to establish the needs and new trends in the training and education of nuclear power plants personnel. The topics treated at the conference can be divided into three basic groups as follows: 1. professional qualification of nuclear power plant staff members; 2. development of technical means for the nuclear power plants personnel training; and 3. training of maintenance personnel, the system and organization of this training and education. The proceedings are published in two volumes. Part 1 contains the texts of 25 papers falling in the INIS subject scope. (Z.M.)

  2. Power Systems Development Facility

    Energy Technology Data Exchange (ETDEWEB)

    None

    2003-07-01

    This report discusses Test Campaign TC12 of the Kellogg Brown & Root, Inc. (KBR) Transport Gasifier train with a Siemens Westinghouse Power Corporation (SW) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Gasifier is an advanced circulating fluidized-bed reactor designed to operate as either a combustor or a gasifier using a particulate control device (PCD). While operating as a gasifier, either air or oxygen can be used as the oxidant. Test run TC12 began on May 16, 2003, with the startup of the main air compressor and the lighting of the gasifier start-up burner. The Transport Gasifier operated until May 24, 2003, when a scheduled outage occurred to allow maintenance crews to install the fuel cell test unit and modify the gas clean-up system. On June 18, 2003, the test run resumed when operations relit the start-up burner, and testing continued until the scheduled end of the run on July 14, 2003. TC12 had a total of 733 hours using Powder River Basin (PRB) subbituminous coal. Over the course of the entire test run, gasifier temperatures varied between 1,675 and 1,850 F at pressures from 130 to 210 psig.

  3. Radiological design criteria for fusion power test facilities

    International Nuclear Information System (INIS)

    Singh, M.S.; Campbell, G.W.

    1982-01-01

    The quest for fusion power and understanding of plasma physics has resulted in planning, design, and construction of several major fusion power test facilities, based largely on magnetic and inertial confinement concepts. We have considered radiological design aspects of the Joint European Torus (JET), Livermore Mirror and Inertial Fusion projects, and Princeton Tokamak. Our analyses on radiological design criteria cover acceptable exposure levels at the site boundary, man-rem doses for plant personnel and population at large, based upon experience gained for the fission reactors, and on considerations of cost-benefit analyses

  4. Power Consumption Analysis of Electrical Installations at Healthcare Facility

    Directory of Open Access Journals (Sweden)

    Emmanuel Guillen-Garcia

    2017-01-01

    Full Text Available This paper presents a methodology for power consumption estimation considering harmonic and interharmonic content and then it is compared to the power consumption estimation commonly done by commercial equipment based on the fundamental frequency, and how they can underestimate the power consumption considering power quality disturbances (PQD. For this purpose, data of electrical activity at the electrical distribution boards in a healthcare facility is acquired for a long time period with proprietary equipment. An analysis in the acquired current and voltage signals is done, in order to compare the power consumption centered in the fundamental frequency with the generalized definition of power consumption. The results obtained from the comparison in the power consumption estimation show differences between 4% and 10% of underestimated power consumption. Thus, it is demonstrated that the presence of harmonic and interharmonic content provokes a significant underestimation of power consumption using only the power consumption centered at the fundamental frequency.

  5. The concept of electro-nuclear facility for useful power generation and minor actinides transmutation

    Energy Technology Data Exchange (ETDEWEB)

    Bergelson, B.R.; Balyuk, S.A. [ITEP, Moscow (Russian Federation)

    1995-10-01

    The possibility is shown to design in principle the double-purpose liquid fuel electro nuclear facility for useful power generation and minor actinides transmutation in U-Pu fuel cycle conditions. D{sub 2}O and a melt of fluorine salts are considered as a working media for liquid fuel. Such facility replenished with depicted or natural uranium only makes it possible to generate power of 900 MW (c) for external consumers and serve 20 WWER-1000 reactors for transmutation of MA. The facility could be thought as an alternative to fast reactors since appr. 30% of the total power confined in uranium is utilized in it.

  6. Proposed power upgrade of the hot fuel examination facility's neutron radiography reactor

    International Nuclear Information System (INIS)

    Pruett, D.P.; Richards, W.J.; Heidel, C.C.

    1984-01-01

    The Hot Fuel Examination Facility, HFEF, is one of several facilities located at the Argonne Site. HFEF comprises a large hot cell where both non-destructive and destructive examination of highly-irradiated reactor fuels are conducted in support of the LMFBR program. One of the non-destructive examination techniques utilized at HFEF is neutron radiography. When the NRAD facility was designed and constructed, an operating power level of 250 kw was considered to be adequate for obtaining radiographs of the type of specimens envisaged at that time. Since that time, several things have occurred that have tended to increase radiography exposure times to as much as 90 minutes each. In order to decrease exposure times, the reactor power level is to be increased from 250 kW to 1 MW. This increase in power will necessitate several engineering and design changes. The proposed upgrade of the NRAD facility will increase the neutron flux available in the beam tubes appreciably. The increased flux will enable NRAD to continue to meet its operational commitments in a timely manner and to develop state-of-the-art techniques in the future as it has in the past

  7. Power Systems Development Facility. Quarterly report, July 1--September 30, 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    This quarterly technical progress report summarizes the work completed during the third quarter of a project entitled Hot Gas Cleanup Test Facility for Gasification and Pressurized Combustion. The objective of this project is to evaluate hot gas particle control technologies using coal-derived gas streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particulate control device issues to be addressed include the integration of the particulate control devices into coal utilization systems, on-line cleaning techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a function of particle size, and scale-up of particulate control systems to commercial size. The conceptual design of the facility was extended to include a within scope, phase expansion of the existing Hot Gas Cleanup Test Facility Cooperative Agreement to also address systems integration issues of hot particulate removal in advanced coal-based power generation systems. This expansion included the consideration of the following modules at the test facility in addition to the original Transport Reactor gas source and Hot Gas Cleanup Units: carbonizer/pressurized circulating fluidized bed gas source; hot gas cleanup units to mate to all gas streams; combustion gas turbine; and fuel cell and associated gas treatment. This expansion to the Hot Gas Cleanup Test Facility is herein referred to as the Power Systems Development Facility (PSDF).

  8. Proceeding of the 7. Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities

    International Nuclear Information System (INIS)

    Hastowo, Hudi; Antariksawan, Anhar R.; Soetrisnanto, Arnold Y; Jujuratisbela, Uju; Aziz, Ferhat; Su'ud, Zaki; Suprawhardana, M. Salman

    2002-02-01

    The seventh proceedings of seminar safety and technology of nuclear power plant and nuclear facilities, held by National Nuclear Energy Agency. The Aims of seminar is to exchange and disseminate information about safety and nuclear Power Plant Technology and Nuclear Facilities consist of technology; high temperature reactor and application for national development sustain able and high technology. This seminar level all aspects technology, Power Reactor research reactor, high temperature reactor and nuclear facilities. The article is separated by index

  9. 18 CFR 292.208 - Special requirements for hydroelectric small power production facilities located at a new dam or...

    Science.gov (United States)

    2010-04-01

    ... for hydroelectric small power production facilities located at a new dam or diversion. 292.208 Section... requirements for hydroelectric small power production facilities located at a new dam or diversion. (a) A hydroelectric small power production facility that impounds or diverts the water of a natural watercourse by...

  10. The enforcement order for the law for arrangement of surrounding areas of power generating facilities

    International Nuclear Information System (INIS)

    1984-01-01

    The enforcement order provides for grants concerning the arrangement of various public facilities in the areas surrounding a power generating facility; the public facilities in the arrangement for which the grants are given include communication, recreation activities, environmental sanitation, culture, medicine, etc. The prefectural governor concerned submits his plan for the arrangement to the Government, which then decides on the grants. Then, the grants are given to local governments concerned. The sums of the grants are determined on the basis of the output, construction cost of the nuclear power facility. (Mori, K.)

  11. Smart Power Supply Systems for Mission Critical Facilities

    Science.gov (United States)

    Hirose, Keiichi; Babasaki, Tadatoshi

    To develop the advanced and rich life, and the also economy and social activity continuously, various types of energy are necessary. At the same time, to protect the global environment and to prevent the depletion of natural resources, the effective and moreover efficient use of energy is becoming important. Electric power is one of the most important forms of energy for our life and society. This paper describes topics and survey results of technical trends regarding the electric power supply systems which are playing a core role as the important infrastructure to support the emergence of information-oriented society. Specifically, the power supply systems that enhance high power quality and reliability (PQR) are important for the steady growth of information and communication services. The direct current (DC) power, which has been used for telecommunications power systems and information and communications technologies (ICT), enables existing utilities' grid and distributed energy resources to keep a balance between supply and demand of small-scaled power systems or microgirds. These techniques are expected to be part of smartgrid technologies and facilitate the installation of distributed generators in mission critical facilities.

  12. Overview of power plant and industrial facility performance in earthquakes in 1985 through 1987

    International Nuclear Information System (INIS)

    Horstman, N.G.; Yanev, P.I.; McCormick, D.L.

    1987-01-01

    This paper briefly documents the performance of power and industrial facilities during five destructive earthquakes in 1985 and 1986. These earthquakes represent varying levels of intensity, duration, frequency content, epicentral distance and construction practice. All of the earthquakes reinforce the findings of earlier earthquake investigations. Damage to equipment in power and industrial facilities is rare, as long as the equipment is adequately anchored. The ceramic components of switchyard equipment and the actuation of electro-mechanical relays remain concerns in the design of facilities which must remain operational during and following strong motion earthquakes. (orig.)

  13. Data acquisition system for medium power neutral beam test facility

    International Nuclear Information System (INIS)

    Stewart, C.R. Jr.; Francis, J.E. Jr.; Hammons, C.E.; Dagenhart, W.K.

    1978-06-01

    The Medium Power Neutral Beam Test Facility at Oak Ridge National Laboratory was constructed in order to develop, test, and condition powerful neutral beam lines for the Princeton Large Torus experiment at Princeton Plasma Physics Laboratory. The data acquisition system for the test stand monitors source performance, beam characteristics, and power deposition profiles to determine if the beam line is operating up to its design specifications. The speed of the computer system is utilized to provide near-real-time analysis of experimental data. Analysis of the data is presented as numerical tabulation and graphic display

  14. 18 CFR 292.209 - Exceptions from requirements for hydroelectric small power production facilities located at a new...

    Science.gov (United States)

    2010-04-01

    ... requirements for hydroelectric small power production facilities located at a new dam or diversion. 292.209... Exceptions from requirements for hydroelectric small power production facilities located at a new dam or... the Federal Power Act, at which non-Federal hydroelectric development is permissible; or (2) An...

  15. 76 FR 51961 - Brown Bear Power, LLC, Topsham Hydroelectric Generating Facility Trust No. 1, Topsham Hydro...

    Science.gov (United States)

    2011-08-19

    ... On August 3, 2011, Brown Bear Power, LLC, Topsham Hydroelectric Generating Facility (Trust No. 1... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Project No. 4784-082] Brown Bear Power, LLC, Topsham Hydroelectric Generating Facility Trust No. 1, Topsham Hydro Partners Limited Partnership...

  16. Deployment of Radioactive Waste Disposal Facility with the Introduction of Nuclear Power Plants in Kenya

    Energy Technology Data Exchange (ETDEWEB)

    Shadrack, Antoony; Kim, Changlak [KEPCO International Nuclear Graduate School, Uljin (Korea, Republic of)

    2013-07-01

    The nuclear power program will inevitably generate radioactive wastes including low-and intermediate radioactive waste and spent fuel. These wastes are hazardous to human health and the environment and therefore, a reliable radioactive waste disposal facility becomes a necessity. This paper describes Kenya's basic plans for the disposal of radioactive wastes expected from the nuclear program. This plan is important as an initial implementation of a national Low to intermediate level wastes storage facility in Kenya. In Kenya, radioactive waste is generated from the use of radioactive materials in medicine, industry, education and research and development. Future radioactive waste is expected to arise from nuclear reactors, oil exploration, radioisotope and fuel production, and research reactors as shown in table 1. The best strategy is to store the LILW and spent fuel temporarily within reactor sites pending construction of a centralized interim storage facility or final disposal facility. The best philosophy is to introduce both repository and nuclear power programs concurrently. Research and development on volume reduction technology and conceptual design of disposal facility of LILW should be pursued. Safe management of radioactive waste is a national responsibility for sustainable generation of nuclear power. The republic of Kenya is set to become the second African nuclear power generation country after South Africa.

  17. 75 FR 76055 - Nebraska Public Power District Cooper Nuclear Station; Notice of Issuance of Renewed Facility...

    Science.gov (United States)

    2010-12-07

    ... NUCLEAR REGULATORY COMMISSION Docket No. 50-298; NRC-2008-0617] Nebraska Public Power District Cooper Nuclear Station; Notice of Issuance of Renewed Facility Operating License No. DPR-46 for an... Power District (NPPD), the operator of the Cooper Nuclear Station (CNS). Renewed facility operating...

  18. Proceedings of the 9. National Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities

    International Nuclear Information System (INIS)

    Antariksawan, Anhar R.; Soetrisnanto, Arnold Y; Aziz, Ferhat; Untoro, Pudji; Su'ud, Zaki; Zarkasi, Amin Santoso; Lasman, As Natio

    2003-08-01

    The ninth proceedings of seminar safety and technology of nuclear power plant and nuclear facilities held by National Nuclear Energy Agency and PLN-JTK. The aims of seminar is to exchange and disseminate information about Safety and Nuclear Power Plant Technology and Nuclear Facilities consist of Technology High Temperature Reactor and Application for National Development Sustainable and High Technology. This seminar cover all aspects Technology, Power Reactor, Research Reactor High Temperature Reactor and Nuclear Facilities. There are 20 articles have separated index

  19. IAEA Director General visits purification facility at Polish thermal power station

    International Nuclear Information System (INIS)

    2001-01-01

    On the occasion of his first visit to Poland, the Director General of the IAEA visited an industrial scale Electron Beam Demonstration facility constructed with IAEA assistance at the Pomorzany Electric Power Station near Szczecin. The facility uses an electron beam device to purify gas effluents from coal burning. By the addition of ammonia, the process permits the production of fertilizer as a by-product. This is an excellent example of how nuclear techniques can be used to reduce the emissions from conventional power plants. Experience gained will help to demonstrate the environmental effectiveness and economic competitiveness of this technology and serve to illustrate how the IAEA in cooperation with Member States can provide advanced nuclear technique to industrial companies

  20. Issues of improving quality of training personnel for nuclear power facilities

    International Nuclear Information System (INIS)

    Jacko, J.

    1987-01-01

    The basic stages are characterized of the development of a standard system of personnel training for the start-up, operation and maintenance of nuclear power facilities. The experience is analyzed gained by the Branch Training Centre of the Nuclear Power Plant Research Institute. Suggestions are submitted for improving the quality of personnel training based on Czechoslovak and foreign experiences. (author). 3 refs

  1. Detailed description of an SSAC at the facility level for on-load refueled power reactor facilities

    International Nuclear Information System (INIS)

    Jones, R.J.

    1985-11-01

    The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in an on-load refueled power reactor facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

  2. Development of high power CW and pulsed RF test facility based on 1 MW, 352.2 MHz klystron amplifier

    International Nuclear Information System (INIS)

    Badapanda, M.K.; Tripathi, Akhilesh; Upadhyay, Rinki; Rao, J.N.; Tiwari, Ashish; Jain, Akhilesh; Lad, M.R.; Hannurkar, P.R.

    2013-01-01

    A high power 1 MW, 352.2 MHz RF Test facility having CW and Pulse capability is being developed at Raja Ramanna Centre for Advanced Technology (RRCAT), Indore for performance evaluation of various RF components, accelerating structures and related subsystems. Thales make 1 MW, 352.2 MHz klystron amplifier (TH 2089) will be employed in this high power test facility, which is thoroughly tested for its performance parameters at rated operating conditions. Auxiliary power supplies like filament, electromagnet, ion pump and mod anode power supply as well as 200 W solid state driver amplifier necessary for this high power test facility have been developed. A high voltage floating platform is created for floating filament and mod anode power supplies. Interconnection of various power supplies and other subsystems of this test facility are being carried out. A high voltage 100 kV, 25 Amp DC crowbar less power supply and low conductivity water (LCW) plant required for this klystron amplifier are in advanced stage of development. NI make cRIO 9081 real time (RT) controller based control and interlock system has been developed to realize proper sequence of operation of various power supplies and to monitor the status of crucial parameters in this test facility. This RF test facility will provide confidence for development of RF System of future accelerators like SNS and ADSS. (author)

  3. Temporary storage facility for spent nuclear fuels at the Atucha I nuclear power station (CNA)

    International Nuclear Information System (INIS)

    Wasinger, K.

    1983-01-01

    According to plans of the Argentine Atomic Energy Commission (CNEA), the spent nuclear fuel elements of the Atucha I Nuclear Power Station are to be stored temporarily pending a decision about the ultimate disposal concept. The holding capacity of the first fuel storage facility built by the German KWU together with the whole power plant had been expanded in 1978 to a level good until mid-1982. In 1977, KWU drafted the concept of another fuel storage facility. Like the first one, it was designed as a wet storage system attached to the power plant installations and had a holding capacity of 6944 fuel elements, which corresponds to some 1100 te of uranium. This extends the storage capacity up until 1996. In 1978, KWU was commissioned by CNEA to plan the whole facility and deliver the mechanical and electrical equipment. CNEA themselves assumed responsibility for the construction work. The second fuel storage facility was commissioned three years after the start of construction. (orig.) [de

  4. 47 CFR 74.795 - Digital low power TV and TV translator transmission system facilities.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 4 2010-10-01 2010-10-01 false Digital low power TV and TV translator... DISTRIBUTIONAL SERVICES Low Power TV, TV Translator, and TV Booster Stations § 74.795 Digital low power TV and TV translator transmission system facilities. (a) A digital low power TV or TV translator station shall operate...

  5. Nuclear space power safety and facility guidelines study

    International Nuclear Information System (INIS)

    Mehlman, W.F.

    1995-01-01

    This report addresses safety guidelines for space nuclear reactor power missions and was prepared by The Johns Hopkins University Applied Physics Laboratory (JHU/APL) under a Department of Energy grant, DE-FG01-94NE32180 dated 27 September 1994. This grant was based on a proposal submitted by the JHU/APL in response to an open-quotes Invitation for Proposals Designed to Support Federal Agencies and Commercial Interests in Meeting Special Power and Propulsion Needs for Future Space Missionsclose quotes. The United States has not launched a nuclear reactor since SNAP 10A in April 1965 although many Radioisotope Thermoelectric Generators (RTGs) have been launched. An RTG powered system is planned for launch as part of the Cassini mission to Saturn in 1997. Recently the Ballistic Missile Defense Office (BMDO) sponsored the Nuclear Electric Propulsion Space Test Program (NEPSTP) which was to demonstrate and evaluate the Russian-built TOPAZ II nuclear reactor as a power source in space. As of late 1993 the flight portion of this program was canceled but work to investigate the attributes of the reactor were continued but at a reduced level. While the future of space nuclear power systems is uncertain there are potential space missions which would require space nuclear power systems. The differences between space nuclear power systems and RTG devices are sufficient that safety and facility requirements warrant a review in the context of the unique features of a space nuclear reactor power system

  6. Regulation for delivery of subsidies for urgent safety measures for atomic power generating facilities

    International Nuclear Information System (INIS)

    1981-01-01

    This rule is established under the provisions of the law for the proper enforcement of subsidy budgets and the ordinance for the execution of this law and to practice these provisions. It is applied to the delivery of subsidies for the expenses of the measures taken beforehand for the security of inhabitants in the surrounding areas of atomic power generating facilities in the emergency time of hazard or the danger of the occurrence of hazard by such facilities. Basic terms are defined, such as atomic power generating facilities and others, prefecture concerned, cities, towns and villages concerned, emergency communication network arrangement business, emergency medical facility arrangement business, business of holding hazard prevention course and expected date of beginning operation. Directors of ministries and agencies concerned deliver, if necessary, to prefectures concerned subsidies for all or a part of the expenses needed for the businesses of emergency communication network arrangement, emergency medical facility arrangement and holding hazard prevention course. The terms of delivery and the amounts of subsidies vary according to the kinds of businesses. Prefectures which intend to apply for the delivery of subsidies shall file to the director of the ministry or agency concerned the specified application attaching the operation plans of businesses and the general explanation of atomic power generating facilities, etc. The decision and conditions of delivery, reports on the situations and results of businesses and other related matters are defined, respectively. (Okada, K.)

  7. Replacement Power Facility site selection report

    Energy Technology Data Exchange (ETDEWEB)

    Wike, L.D.; Toole, G.L.; Specht, W.L.

    1992-06-01

    The Department of Energy (DOE) has proposed the construction and operation of a Replacement Power Facility (RPF) for supplementing and replacing existing sources of steam and possibly electricity at the Savannah River Site (SRS). DOE is preparing an Environmental Impact Statement (EIS) for this project As part of the impact analysis of the proposed action, the EIS will include a detailed description of the environment where the RPF will be constructed. This description must be specific to the recommended site at SRS, which contains more than 300 square miles of land including streams, lakes, impoundments, wetlands, and upland areas. A formal site-selection process was designed and implemented to identify the preferred RPF site.

  8. 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)

  9. Situation of the radioactive waste management and the employee radiation exposure in commercial power generation reactor facilities in fiscal 1980

    International Nuclear Information System (INIS)

    1981-01-01

    (1) Situation of the radioactive waste management in commercial power generating reactor facilities: The owners of power generation reactor facilities are obligated not to exceed the target dose around the sites by law in the radioactive waste management. The release of radioactive gaseous and liquid wastes and the storage of radioactive solid wastes in respective reactor facilities in fiscal 1980 are presented in tables (for the former, the data since 1971 are also given). The release control values were satisfied in all the facilities. (2) Situation of employe radiation exposure in commercial power generating reactor facilities: The owners of power generation reactor facilities are obligated not to exceed the permissible exposure doses by law. The Employe exposure doses in respective reactor facilities in fiscal 1980 are given in tables. All exposure doses were below the permissible levels. (J.P.N.)

  10. Multimegawatt space nuclear power open-cycle MHD-facility

    International Nuclear Information System (INIS)

    Pavshuk, V.A.; Panchenko, V.P.

    2008-01-01

    Paper presents the results of the efforts to calculate the characteristics, the layout and the engineering design of the open cycle space power propulsion on the basis of the high-temperature nuclear reactor for a nuclear rocket engine and the Faraday 20 MW capacity MHD-generator. The IVG-1 heterogeneous channel-vessel reactor ensuring in the course of the experiments hydrogen heating up to 3100 K, up to 5 MPa pressure at the reactor core outlet, up to 5 kg/s flowsheet, up to 220 MW thermal power served as a reactor is considered. One determined the MHD-generator basic parameters, namely: the portion of Cs dope was equal to 20%, the outlet stagnation pressure - 2 MPa, the electric conductivity - ≅30 S/m, the Mach number - ≅0.7, the magnetic field induction - 6 T, the capacity - 20 MW, the specific power removal - ∼4 MJ/kg. Paper describes the design of the MHD-facility with the working fluid momentless discharge and its basic characteristics [ru

  11. Alteration in reactor installations (Unit 1 and 2 reactor facilities) in the Hamaoka Nuclear Power Station of The Chubu Electric Power Co., Inc. (report)

    International Nuclear Information System (INIS)

    1982-01-01

    A report by the Nuclear Safety Commission to the Ministry of International Trade and Industry concerning the alteration in Unit 1 and 2 reactor facilities in the Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., was presented. The technical capabilities for the alteration of reactor facilities in Chubu Electric Power Co., Inc., were confirmed to be adequate. The safety of the reactor facilities after the alteration was confirmed to be adequate. The items of examination made for the confirmation of the safety are as follows: reactor core design (nuclear design, mechanical design, mixed reactor core), the analysis of abnormal transients in operation, the analysis of various accidents, the analysis of credible accidents for site evaluation. (Mori, K.)

  12. The state of improvement of security management setup in the Japan Atomic Power Company and improvement of facilities in its Tsuruga Nuclear Power Station

    International Nuclear Information System (INIS)

    1982-01-01

    In connection with the series of accidents in the Tsuruga Nuclear Power Station of the Japan Atomic Power Company, the state of security management in JAPC and the safety of facilities in the Tsuruga Nuclear Power Station, which have resulted from improvement efforts, are described on the following items: security management setup - communication and reporting in emergency, the management of inspection and maintenance records, work control and supervision in repair, improvement, etc., functional authority and responsibility in maintenance management, operation management, radiation control, personnel education; improvement of facilities - feed water heaters, laundry waste-water filter room, radioactive waste treatment facility, general drainage, concentrated waste liquid storage tanks in newly-built waste treatment building, etc. (Mori, K.)

  13. Nuclear power plant simulation facility evaluation methodology

    International Nuclear Information System (INIS)

    Haas, P.M.; Carter, R.J.; Laughery, K.R. Jr.

    1985-01-01

    A methodology for evaluation of nuclear power plant simulation facilities with regard to their acceptability for use in the US Nuclear Regulatory Commission (NRC) operator licensing exam is described. The evaluation is based primarily on simulator fidelity, but incorporates some aspects of direct operator/trainee performance measurement. The panel presentation and paper discuss data requirements, data collection, data analysis and criteria for conclusions regarding the fidelity evaluation, and summarize the proposed use of direct performance measurment. While field testing and refinement of the methodology are recommended, this initial effort provides a firm basis for NRC to fully develop the necessary methodology

  14. Final environmental assessment for a refinement of the power delivery component of the Southern Nevada Water Authority Treatment and Transmission Facility

    International Nuclear Information System (INIS)

    1998-07-01

    The Southern Nevada Water Authority (SNWA) is designing and constructing a system of regional water supply facilities to meet current and projected water demands and increase system reliability. The existing Southern Nevada Water system is being upgraded with a number of improvements to increase the capacity of the system. However, even the expanded system is expected to be unable to meet projected peak daily water demands by the year 1999. As a result, new facilities are being designed and constructed to operate in conjunction with the upgraded Southern Nevada Water system. These new facilities, known as the Southern Nevada Water Authority Treatment and Transmission Facility (SNWA-TTF), include four primary components: a new raw water intake; new transmission facilities including below ground pipelines, tunnels, and above ground pumping stations; a water treatment facility; and new power supply facilities. Because existing power supplies would not be adequate for the new water treatment facilities, new power facilities, consisting of two new 230 kV-69 kV substations and new 69 and 230 kV power lines, are being constructed. This environmental assessment is specifically on the new power facilities

  15. Electromagnetic Fields Associated with Commercial Solar Photovoltaic Electric Power Generating Facilities.

    Science.gov (United States)

    Tell, R A; Hooper, H C; Sias, G G; Mezei, G; Hung, P; Kavet, R

    2015-01-01

    The southwest region of the United States is expected to experience an expansion of commercial solar photovoltaic generation facilities over the next 25 years. A solar facility converts direct current generated by the solar panels to three-phase 60-Hz power that is fed to the grid. This conversion involves sequential processing of the direct current through an inverter that produces low-voltage three-phase power, which is stepped up to distribution voltage (∼12 kV) through a transformer. This study characterized magnetic and electric fields between the frequencies of 0 Hz and 3 GHz at two facilities operated by the Southern California Edison Company in Porterville, CA and San Bernardino, CA. Static magnetic fields were very small compared to exposure limits established by IEEE and ICNIRP. The highest 60-Hz magnetic fields were measured adjacent to transformers and inverters, and radiofrequency fields from 5-100 kHz were associated with the inverters. The fields measured complied in every case with IEEE controlled and ICNIRP occupational exposure limits. In all cases, electric fields were negligible compared to IEEE and ICNIRP limits across the spectrum measured and when compared to the FCC limits (≥0.3 MHz).

  16. The regulation for delivery of subsidies for measures of promoting power source location for nuclear power generating facilities

    International Nuclear Information System (INIS)

    1984-01-01

    According to the law for the arrangement of surrounding areas of power generating facilities, the regulations concern the allocation of subsidies to promote the most efficient way of siting nuclear power facilities. The contents consist of the following: limits on the subsidies, terms of subsidy allocations, the sum of subsidies for each respective year, applications for subsidies, determination of subsidy allocations, withdrawal of applications, the conditions attached to the allocations, a report on the work proceedings, a report on the results, confirmation on the sum of the subsidies, withdrawal of the decision for subsidies, limitations for disposal of the properties, payment of subsidies, accounting of the subsidy operations, a record of the subsidies, and the chief in the governmental office concerned. (Mori, K.)

  17. Safety issues relating to the design of fusion power facilities

    International Nuclear Information System (INIS)

    Stasko, R.R.; Wong, K.Y.; Russell, S.B.

    1986-06-01

    In order to make fusion power a viable future source of energy, it will be necessary to ensure that the cost of power for fusion electric generation is competitive with advanced fission concepts. In addition, fusion power will have to live up to its original promise of being a more radiologically benign technology than fission, and be able to demonstrate excellent operational safety performance. These two requirements are interrelated, since the selection of an appropriate safety philosophy early in the design phase could greatly reduce or eliminate the capital costs of elaborate safety related and protective sytems. This paper will briefly overview a few of the key safety issues presently recognized as critical to the ultimate achievement of licensable, environmentally safe and socially acceptable fusion power facilities. 12 refs

  18. Upgrade of DC power supply system in ITER CS model coil test facility

    International Nuclear Information System (INIS)

    Shimono, Mitsugu; Uno, Yasuhiro; Yamazaki, Keita; Kawano, Katsumi; Isono, Takaaki

    2014-03-01

    Objective of the ITER CS Model Coil Test Facility is to evaluate a large scale superconducting conductor for fusion using the Central Solenoid (CS) Model Coil, which can generate a 13T magnetic field in the inner bore with a 1.5 m diameter. The facility is composed of a helium refrigerator / liquefier system, a DC power supply system, a vacuum system and a data acquisition system. The DC power supply system supplies currents to two superconducting coils, the CS Model Coil and an insert coil. A 50-kA DC power supply is installed for the CS Model Coil and two 30 kA DC power supplies are installed for an insert coil. In order to evaluate superconducting performance of a conductor used for ITER Toroidal Field (TF) coils whose operating current is 68 kA, the line for an insert coil is upgraded. A 10 kA DC power supply was added, DC circuit breakers were upgraded, bus bars and current measuring instrument were replaced. In accordance to the upgrade, operation manual was revised. (author)

  19. Outline of construction and facility features of Onagawa nuclear power station Unit No. 2

    International Nuclear Information System (INIS)

    Umimura, Yoshiharu; Tsunoda, Ryohei; Watanabe, Kazunori

    1996-01-01

    Tohoku Electric Power Company promotes development of various power sources to provide a stable supply of electricity in the future, and nuclear power takes a leading part. In August 1989, construction of Onagawa nuclear power plant Unit No. 2 (825MW) was started, following Unit No. 1 (524MW) which went on line in 1984 as Tohoku Electric's first nuclear power plant unit. Unit No. 2 began commercial operation in July 1995 through satisfactory construction work such as RPV hydraulic test in March 1994, fuel loading in October 1994, and various startup tests in each power stage. The design and construction of Unit No. 2 reflect construction and operation experience gained from Unit No. 1, and the latest technology, including that of the LWR Improvement and Standardization Program, was adopted to enhance facility reliability, improve operation and maintenance performance, and reduce worker dosage. Features of the facility, construction techniques, and a description of preoperation of Onagawa nuclear power plant Unit No. 2 are described in this paper. (author)

  20. Facilities for treatment of radioactive contaminated water in nuclear power plants

    International Nuclear Information System (INIS)

    1981-02-01

    The standard applies to processes applied in facilities for treatment of radioactive contaminated water in nuclear power plants with LWR- and HTR-type reactors. It does not apply to the treatment of concentrates obtained in the decontamination of water. (orig.) [de

  1. 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)

  2. The National Carbon Capture Center at the Power Systems Development Facility

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2014-12-30

    The National Carbon Capture Center (NCCC) at the Power Systems Development Facility supports the Department of Energy (DOE) goal of promoting the United States’ energy security through reliable, clean, and affordable energy produced from coal. Work at the NCCC supports the development of new power technologies and the continued operation of conventional power plants under CO2 emission constraints. The NCCC includes adaptable slipstreams that allow technology development of CO2 capture concepts using coal-derived syngas and flue gas in industrial settings. Because of the ability to operate under a wide range of flow rates and process conditions, research at the NCCC can effectively evaluate technologies at various levels of maturity and accelerate their development path to commercialization. During its first contract period, from October 1, 2008, through December 30, 2014, the NCCC designed, constructed, and began operation of the Post-Combustion Carbon Capture Center (PC4). Testing of CO2 capture technologies commenced in 2011, and through the end of the contract period, more than 25,000 hours of testing had been achieved, supporting a variety of technology developers. Technologies tested included advanced solvents, enzymes, membranes, sorbents, and associated systems. The NCCC continued operation of the existing gasification facilities, which have been in operation since 1996, to support the advancement of technologies for next-generation gasification processes and pre-combustion CO2 capture. The gasification process operated for 13 test runs, supporting over 30,000 hours combined of both gasification and pre-combustion technology developer testing. Throughout the contract period, the NCCC incorporated numerous modifications to the facilities to accommodate technology developers and increase test capabilities. Preparations for further testing were ongoing to continue advancement of the most promising technologies for

  3. Power systems development facility. Quarterly technical progress report, July 1--September 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-31

    This quarterly technical progress report summarizes work completed during the Second Quarter of the Second Budget Period, July 1 through September 30, 1993, under the Department of Energy (DOE) Cooperative Agreement No. DE-FC21-90MC25140 entitled ``Hot Gas Cleanup Test Facility for Gasification and Pressurized Combustion.`` The objective of this project is to evaluate hot gas particle control technologies using coal-derived gas streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particulate control device issues to be addressed include the integration of the particulate control devices into coal utilization systems, on-line cleaning techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a function of particle size, and scaleup of particulate control systems to commercial size. The conceptual design of the facility was extended to include a within scope, phased expansion of the existing Hot Gas Cleanup Test Facility Cooperative Agreement to also address systems integration issues of hot particulate removal in advanced coal-based power generation systems. This expansion included the consideration of the following modules at the test facility in addition to the existing Transport Reactor gas source and Hot Gas Cleanup Units: Carbonizer/Pressurized Circulating Fluidized Bed Gas Source. Hot Gas Cleanup Units to mate to all gas streams; Combustion Gas Turbine; and Fuel Cell and associated gas treatment. This expansion to the Hot Gas Cleanup Test Facility is herein referred to as the Power Systems Development Facility (PSDF). The major emphasis during this reporting period was continuing the detailed design of the facility.

  4. POWER SYSTEMS DEVELOPMENT FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Unknown

    2002-11-01

    This report discusses test campaign GCT4 of the Kellogg Brown & Root, Inc. (KBR) transport reactor train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The transport reactor is an advanced circulating fluidized-bed reactor designed to operate as either a combustor or a gasifier using one of two possible particulate control devices (PCDs). The transport reactor was operated as a pressurized gasifier during GCT4. GCT4 was planned as a 250-hour test run to continue characterization of the transport reactor using a blend of several Powder River Basin (PRB) coals and Bucyrus limestone from Ohio. The primary test objectives were: Operational Stability--Characterize reactor loop and PCD operations with short-term tests by varying coal-feed rate, air/coal ratio, riser velocity, solids-circulation rate, system pressure, and air distribution. Secondary objectives included the following: Reactor Operations--Study the devolatilization and tar cracking effects from transient conditions during transition from start-up burner to coal. Evaluate the effect of process operations on heat release, heat transfer, and accelerated fuel particle heat-up rates. Study the effect of changes in reactor conditions on transient temperature profiles, pressure balance, and product gas composition. Effects of Reactor Conditions on Synthesis Gas Composition--Evaluate the effect of air distribution, steam/coal ratio, solids-circulation rate, and reactor temperature on CO/CO{sub 2} ratio, synthesis gas Lower Heating Value (LHV), carbon conversion, and cold and hot gas efficiencies. Research Triangle Institute (RTI) Direct Sulfur Recovery Process (DSRP) Testing--Provide syngas in support of the DSRP commissioning. Loop Seal Operations--Optimize loop seal operations and investigate increases to previously achieved maximum solids-circulation rate.

  5. Power systems development facility. Quarterly technical progress report, July 1, 1994--September 30, 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    The objective of this project is to evaluate hot gas particle control technologies using coal-derived gas streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particulate control device issues to be addressed include the integration of the particulate control devices into coal utilization systems, on-line cleaning techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a function of particle size, and scale-up of particulate control systems to commercial size. The conceptual design of the facility was extended to include a within scope, phased expansion of the existing Hot Gas Cleanup Test Facility Cooperative Agreement to also address systems integration issues of hot particulate removal in advanced coal-based power generation systems. This expansion included the consideration of the following modules at the test facility in addition to the original Transport Reactor gas source and Hot Gas Cleanup Units: (1) Carbonizer/Pressurized Circulating Fluidized Bed Gas Source. (2) Hot Gas Cleanup Units to mate to all gas streams. (3) Combustion Gas Turbine. (4) Fuel Cell and associated gas treatment. This expansion to the Hot Gas Cleanup Test Facility is herein referred to as the Power Systems Development Facility (PSDF).

  6. Differential infrared thermography applied to power generation facilities -- A case history

    International Nuclear Information System (INIS)

    Kaplan, H.; Zayicek, P.

    1995-01-01

    The controlled and systematic application of differential thermal imaging (DIT) can be a highly promising tool for condition monitoring and predictive maintenance of electronic, electrical and mechanical elements and can dramatically improve the reliability, maintainability and operational life of certain types of elements in the power generation and distribution community. The expanded applicability of this technique has been brought about by improvements in commercial IR thermal imaging equipment and advances in the related data and image processing capacities. This paper summarizes the advantages and limitations of DIT and describes several variations of the technique. It goes on to provide an update of progress on a program initiated by the Electric Power Research Institute (EPRI) Nondestructive Evaluation (NDE) Center to apply DIT to operating elements within a power generating station environment (Wolf Creek Nuclear Facility). It traces the selection of candidate elements at some of EPRI's member facilities, the implementation of exploratory measurements on selected candidates using available on-site infrared imaging equipment and the analysis of significant findings on one specific critical element. Finally, a projection for the potential future applicability of the DIT technique is provided

  7. Coordination Between Wind Power, Hydro Storage Facility and Conventional Generating Units According to the Annual Growth Load

    Directory of Open Access Journals (Sweden)

    Shahrokh Shojaeean

    2013-04-01

    Full Text Available Considering the growing trend of the consumption of the electric power and the global tendency to substitute new renewable sources of energy, this paper proposes a Monte Carlo based method to determine an optimal level of this change. Considering the limitation of the wind farms in continuous supply of electric power, hydrostatic power storage facilities are used beside wind farms so that the electric power could be stored and fed in a continuous flow into power systems. Due to the gradual exclusion of conventional generators and 5 percent annual load increments, LOLE index was used in order to calculate the amount of the wind power and the capacity of the necessary power storage facility. To this end, LOLE index was calculated for the first year as the reference index for the estimation of the amount of wind power and the capacity of the storage facility in consequent years. For the upcoming years, calculations have been made to account for the gradual exclusion of conventional generators in proportion to load increments. The proposed method has been implemented and simulated on IEEE-RTS test system.

  8. Design and development of microcontroller based programmable ramp generator for AC-DC converter for simulating decay power transient in experimental facility for nuclear power plants

    International Nuclear Information System (INIS)

    Srivastava, Gaurava Deep; Kulkarni, R.D.

    2015-01-01

    In nuclear power plants, fuel is subjected to a wide range of power and temperature transients during normal and abnormal conditions. The reactor setback and step-back power pattern, fast temperature profile occurred during Loss of Coolant Accident and decay power followed by shutdown of power plant are the typical transients in nuclear power plant. For a variety of reactor engineering and reactor safety related study, one needs to simulate these transients in experimental facility. In experimental facilities, high response AC-DC converters are used to handle these power and temperature transients safely in a controlled manner for generating a database which is utilized for design of thermal hydraulic system, development of computer codes, study of reliability of reactor safety system, etc. for nuclear power plants. The paper presents the methodology developed for simulating the typical reactor decay power transient in an experimental facility. The design and simulation of AC-DC power electronic converter of 3 MW capacity is also presented. The microcontroller based programmable ramp generator is designed and hardware implemented for feeding reference voltage to the closed loop control system of AC-DC converter for obtaining the decay power profile at the converter output. The typical decay power transient of the nuclear power plant is divided into several small power ramps for simulating the transient. The signal corresponding to each power ramp is generated by programmable ramp generator and fed to the comparator for generating control signal for the converter. The actual decay power transient obtained from the converter is compared with the theoretical decay power transient. (author)

  9. The regulation for delivery of subsidies for measures of promoting power source location for nuclear power generating facilities

    International Nuclear Information System (INIS)

    1979-01-01

    The regulation is defined under the law for arrangement of surrounding areas of power generating facilities and the law concerning subsidies and others. Limits of the subsidies are stipulated respectively for establishment of a unit and simultaneous construction of more than 2 units of power generating facilities in the area of self-governing bodies concerned. Limits of the subsidies for an arrangement business out of the area of self-governing bodies where the facilities are set up shall be equal to those of the subsidies for such bodies. The Director General of Science and Technology Agency and the Minister of International Trade and Industry may make the amounts otherwise determined the limits of the subsidies, when considered necessary successfully to build the facilities. The term of delivery is from a fiscal year in which a later one of either the day of beginning of the construction concerned or the day of acknowledgment of the arrangement program of the business is included, through a fiscal year when the work finishes. An application for subsidies shall be filed to the head of the authorities concerned with gists of the business according to the forms attached. Receiving the application, the head of the authorities shall examine it and notify to the applicant without delay in writing the decision of delivery and its conditions, when such settlement is made. (Okada, K.)

  10. Proceedings of the 8. National Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities

    International Nuclear Information System (INIS)

    Antariksawan, Anhar R.; Soetrisnanto, Arnold Y.; Aziz, Ferhat; Untoro, Pudji; Su'ud, Zaki; Zarkasi, Amin Santosa; Umar, Faraz H.; Teguh Bambang; Hafnan, M.; Mustafa, Bustani; Rosfian, H.

    2002-10-01

    The eight proceeding of National Seminar on Technology and Safety of Nuclear Power Plant and Nuclear Facilities held by National Atomic Energy Agency and University of Trisakti. The aims of Seminar is to exchange and disseminate information about safety and nuclear Power Plant Temperature Reactor and Application for National Development sustain able and High Technology. This Seminar covers all aspect Technology, Power Reactor : Research Reactor; High Temperature Reactor and Nuclear Facilities. There are 33 articles have separated index

  11. Development of 3He-BOCA power ramping facility, 1

    International Nuclear Information System (INIS)

    Nakata, Hirokatsu; Ishii, Tadahiko; Itoh, Haruhiko; Abe, Hiroshi; Nakazaki, Chozaburo

    1979-11-01

    Development of a He-3 power controlled boiling water capsule, 3 He-BOCS, for LWR fuels power ramping test in JMTR has been carried out since 1978 on a five-year program; in the reactor, irradiation tests of various fuels and structual materials have been made since 1969. Using stagnant-pressurized water as a thermal medium, the capsule provides pressure and temperature conditions similar to those in LWRs. Heat generation of a fuel pin can be controlled by a He-3 gas screen surrounding the capsule. The facility is capable of testing numbers of both fresh and irradiated fuel pins under LWR operating conditions for power ramping and cycling. After explaining the operating priciples of 3 He-BOCA and the development program, the following are described: the results of preliminary out-of-pile test on heat conductive characteristics of the capsule and a conceptual design of the 3 He-BOCA for power ramping of a short fuel pin from 250 W/cm to 500 W/cm under BWR conditions. (author)

  12. Design and Testing of a Breadboard Electrical Power Control Unit for the Fluid Combustion Facility Experiment

    Science.gov (United States)

    Kimnach, Greg L.; Lebron, Ramon C.

    1999-01-01

    The Fluid Combustion Facility (FCF) Project and the Power Technology Division at the NASA Glenn Research Center (GRC) at Lewis Field in Cleveland, OH along with the Sundstrand Corporation in Rockford, IL are jointly developing an Electrical Power Converter Unit (EPCU) for the Fluid Combustion Facility to be flown on the International Space Station (ISS). The FCF facility experiment contains three racks: A core rack, a combustion rack, and a fluids rack. The EPCU will be used as the power interface to the ISS 120V(sub dc) power distribution system by each FCF experiment rack which requires 28V(sub dc). The EPCU is a modular design which contains three 120V(sub dc)-to-28V(sub dc) full-bridge, power converters rated at 1 kW(sub e) each bus transferring input relays and solid-state, current-limiting input switches, 48 current-limiting, solid-state, output switches; and control and telemetry hardware. The EPCU has all controls required to autonomously share load demand between the power feeds and--if absolutely necessary--shed loads. The EPCU, which maximizes the usage of allocated ISS power and minimizes loss of power to loads, can be paralleled with other EPCUs. This paper overviews the electrical design and operating characteristics of the EPCU and presents test data from the breadboard design.

  13. Sustaining neutral beam power supply system for the Mirror Fusion Test Facility

    International Nuclear Information System (INIS)

    Eckard, R.D.; Wilson, J.H.; Van Ness, H.W.

    1980-01-01

    In late August 1978, a fixed price procurement contract for $25,000,000 was awarded to Aydin Energy Division, Palo Alto, California, for the design, manufacture, installation and acceptance testing of the Lawrence Livermore National Laboratory Mirror Fusion Test Facility (MFTF) Sustaining Neutral Beam Power Supply System (SNBPSS). This system of 24 power supply sets will provide the conditioned power for the 24 neutral beam source modules. Each set will provide the accel potential the arc power, the filament power, and the suppressor power for its associated neutral beam source module. The design and development of the SNBPSS has progressed through the final design phase and is now in production. Testing of the major sub-assembly power supply is proceeding at Aydin and the final acceptance testing of the first two power supplies at LLNL is expected to be completed this year

  14. Administrative limits for tritium concentrations found in non-potable groundwater at nuclear power facilities

    International Nuclear Information System (INIS)

    Parker, R.; Hart, D.; WIllert, C.

    2012-01-01

    Currently, there is a regulatory limit available for tritium in drinking water, but no such limit for non-potable groundwater. Voluntary administrative limits for site groundwater may be established at nuclear power facilities to ensure minimal risk to human health and the environment, and provide guidance for investigation or other actions intended to prevent exceedances of future regulatory or guideline limits. This work presents a streamlined approach for nuclear power facilities to develop three tiers of administrative limits for tritium in groundwater so that facilities can identify abnormal/uncontrolled releases of tritium at an early stage, and take appropriate actions to investigate, control, and protect groundwater. Tier 1 represents an upper limit of background, Tier 2 represents a level between background and Tier 3, and Tier 3 represents a risk-based concentration protective of down-gradient receptors. (author)

  15. A new digital pulse power supply in heavy ion research facility in Lanzhou

    Science.gov (United States)

    Wang, Rongkun; Chen, Youxin; Huang, Yuzhen; Gao, Daqing; Zhou, Zhongzu; Yan, Huaihai; Zhao, Jiang; Shi, Chunfeng; Wu, Fengjun; Yan, Hongbin; Xia, Jiawen; Yuan, Youjin

    2013-11-01

    To meet the increasing requirements of the Heavy Ion Research Facility in Lanzhou-Cooler Storage Ring (HIRFL-CSR), a new digital pulse power supply, which employs multi-level converter, was designed. This power supply was applied with a multi H-bridge converters series-parallel connection topology. A new control model named digital power supply regulator system (DPSRS) was proposed, and a pulse power supply prototype based on DPSRS has been built and tested. The experimental results indicate that tracking error and ripple current meet the requirements of this design. The achievement of prototype provides a perfect model for HIRFL-CSR power supply system.

  16. Occupational radiation exposure at commercial nuclear power reactors and other facilities, 1990: Twenty-third annual report

    International Nuclear Information System (INIS)

    Raddatz, C.T.

    1993-01-01

    This report summarizes the occupational radiation exposure information that has been reported to the NRC's Radiation Exposure Information Reporting System (REIRS) by nuclear power facilities and certain other categories of NRC licensees during the years 1969 through 1990. The bulk of the data presented in the report was obtained from annual radiation exposure reports submitted in accordance with the requirements of 10 CFR 20.407 and the technical specifications of nuclear power plants. Data on workers terminating their employment at certain NRC licensed facilities were obtained from reports submitted pursuant to 10 CFR 20.408. The 1990 annual reports submitted by about 443 licensees indicated that approximately 214,568 individuals were monitored, 110,204 of whom were monitored by nuclear power facilities. They incurred an average individual dose of 0.19 rem (cSv) and an average measurable dose of about 0.36 (cSv). Termination radiation exposure reports were analyzed to reveal that about 113,361 individuals completed their employment with one or more of the 443 covered licensees during 1990. Some 77,633 of these individuals terminated from power reactor facilities, and about 11,083 of them were considered to be transient workers who received an average dose of 0.67 rem (cSv)

  17. Helium turbomachinery operating experience from gas turbine power plants and test facilities

    International Nuclear Information System (INIS)

    McDonald, Colin F.

    2012-01-01

    The closed-cycle gas turbine, pioneered and deployed in Europe, is not well known in the USA. Since nuclear power plant studies currently being conducted in several countries involve the coupling of a high temperature gas-cooled nuclear reactor with a helium closed-cycle gas turbine power conversion system, the experience gained from operated helium turbomachinery is the focus of this paper. A study done as early as 1945 foresaw the use of a helium closed-cycle gas turbine coupled with a high temperature gas-cooled nuclear reactor, and some two decades later this was investigated but not implemented because of lack of technology readiness. However, the first practical use of helium as a gas turbine working fluid was recognized for cryogenic processes, and the first two small fossil-fired helium gas turbines to operate were in the USA for air liquefaction and nitrogen production facilities. In the 1970's a larger helium gas turbine plant and helium test facilities were built and operated in Germany to establish technology bases for a projected future high efficiency large nuclear gas turbine power plant concept. This review paper covers the experience gained, and the lessons learned from the operation of helium gas turbine plants and related test facilities, and puts these into perspective since over three decades have passed since they were deployed. An understanding of the many unexpected events encountered, and how the problems, some of them serious, were resolved is important to avoid them being replicated in future helium turbomachines. The valuable lessons learned in the past, in many cases the hard way, particularly from the operation in Germany of the Oberhausen II 50 MWe helium gas turbine plant, and the technical know-how gained from the formidable HHV helium turbine test facility, are viewed as being germane in the context of current helium turbomachine design work being done for future high efficiency nuclear gas turbine plant concepts. - Highlights:

  18. Annual monitoring and surveillance report for Piqua Nuclear Power Facility, Piqua, Ohio

    International Nuclear Information System (INIS)

    Mosho, G.D.

    1991-12-01

    This report discusses the decommissioned Piqua Nuclear Power Facility which is located in Piqua, Ohio near the Greater Miami River. The Facility was built by the US Atomic Energy Commission (now U. S. Department of Energy) and was operated from 1963 to 1966. The reactor was retired prior to 1970 and the facility was leased to the city of Piqua for use as offices and equipment storage. In December 1991, a radiological survey was done of the facility to document its radiological condition. The data show that all radiological parameters measured were essentially the same as that found in the natural environment. The only exception was that low levels of radioactive contamination were detected in one drain on the 56.5 ft elevation, but the radiation exposure rate in that area was also typical of natural background

  19. Strategies for the co-operation between power generation facilities and power sales organisations in the European electricity market

    International Nuclear Information System (INIS)

    Bammert, U.

    2003-01-01

    This article discusses how the public utilities in Hannover, Germany, have developed a strategy for the operation of their power generation facilities and power distribution network as independent yet co-operating units. Three models that were examined are described: 'free-sailing', where generation and distribution were kept completely independent, the 'wedding' model, where they were closely tied together and 'Enercity', a mixture of both models. The various rules necessary and the degrees of freedom needed to implement the 'Enercity' model are discussed, as are the advantages it offers to both the power generation and the sales units

  20. Considerations in the development and implementation of a maintenance robot for nuclear power facilities

    International Nuclear Information System (INIS)

    Rohrabacher, A.; Carlton, R.; Gelhaus, F.

    1987-01-01

    The Nuclear Power Division of the Electric Power Research Institute (EPRI) began its automated nuclear plant maintenance research (research project 2232) in 1982 with surveys of domestic and Japanese ongoing and potential uses of robotic systems in nuclear power facilities. After studying these potential research areas, EPRI initiated a three-pronged effort. All surveys concluded that a mobile system for general environmental, visual, and auto surveillance would be beneficial, and EPRI contracted for the development and evaluation of the Surveyor robot. Work also began to catalog existing systems and to quantify the methodology that a utility could use to optimally complete the plant-mission, robot-system selection process. The conceptualizing phase of the effort defined the necessary physical attributes for the machine to perform a variety of maintenance tasks. Characteristics such as mobility, strength, conditions of service, materials of construction, tool functional requirements, facility interfaces, and operator interface were defined to the extent practical. Substantial versatility is required for the variability of the targeted maintenance tasks and for the variability of facility layouts and designs found throughout the nuclear industry. A key contribution to this development effort comes from the project's Utility Advisors Group. The contract's host utility provides membership to lead this group, and that company will train in the use of the machine for 6 months prior to utilizing it in their power plant for 2 yr

  1. Test facility for investigation of heat transfer of promising coolants for the nuclear power industry

    Science.gov (United States)

    Belyaev, I. A.; Sviridov, V. G.; Batenin, V. M.; Biryukov, D. A.; Nikitina, I. S.; Manchkha, S. P.; Pyatnitskaya, N. Yu.; Razuvanov, N. G.; Sviridov, E. V.

    2017-11-01

    The results are presented of experimental investigations into liquid metal heat transfer performed by the joint research group consisting of specialist in heat transfer and hydrodynamics from NIU MPEI and JIHT RAS. The program of experiments has been prepared considering the concept of development of the nuclear power industry in Russia. This concept calls for, in addition to extensive application of water-cooled, water-moderated (VVER-type) power reactors and BN-type sodium cooled fast reactors, development of the new generation of BREST-type reactors, fusion power reactors, and thermonuclear neutron sources. The basic coolants for these nuclear power installations will be heavy liquid metals, such as lead and lithium-lead alloy. The team of specialists from NRU MPEI and JIHT RAS commissioned a new RK-3 mercury MHD-test facility. The major components of this test facility are a unique electrical magnet constructed at Budker Nuclear Physics Institute and a pressurized liquid metal circuit. The test facility is designed for investigating upward and downward liquid metal flows in channels of various cross-sections in a transverse magnetic field. A probe procedure will be used for experimental investigation into heat transfer and hydrodynamics as well as for measuring temperature, velocity, and flow parameter fluctuations. It is generally adopted that liquid metals are the best coolants for the Tokamak reactors. However, alternative coolants should be sought for. As an alternative to liquid metal coolants, molten salts, such as fluorides of lithium and beryllium (so-called FLiBes) or fluorides of alkali metals (so-called FLiNaK) doped with uranium fluoride, can be used. That is why the team of specialists from NRU MPEI and JIHT RAS, in parallel with development of a mercury MHD test facility, is designing a test facility for simulating molten salt heat transfer and hydrodynamics. Since development of this test facility requires numerical predictions and verification

  2. Dry spent fuel storage facility at Kozloduy Nuclear Power Plant

    International Nuclear Information System (INIS)

    Goehring, R.; Stoev, M.; Davis, N.; Thomas, E.

    2004-01-01

    The Dry Spent Fuel Storage Facility (DSF) is financed by the Kozloduy International Decommissioning Support Fund (KIDSF) which is managed by European Bank for Reconstruction and Development (EBRD). On behalf of the Employer, the Kozloduy Nuclear Power Plant, a Project Management Unit (KPMU) under lead of British Nuclear Group is managing the contract with a Joint Venture Consortium under lead of RWE NUKEM mbH. The scope of the contract includes design, manufacturing and construction, testing and commissioning of the new storage facility for 2800 VVER-440 spent fuel assemblies at the KNPP site (turn-key contract). The storage technology will be cask storage of CONSTOR type, a steel-concrete-steel container. The licensing process complies with the national Bulgarian regulations and international rules. (authors)

  3. An overview of the transportation of radioactive waste at Ontario Power Generation facilities

    International Nuclear Information System (INIS)

    Holmes, P.

    2006-01-01

    The Radioactive Material Transportation Department (RMT) ensures regulatory compliance in radioactive material shipping within Ontario Power Generation (OPG). OPG provides a radioactive shipping program, high quality carrier service, stringent packaging maintenance, and quality assurance oversight to the corporation's nuclear facilities and its customers. This paper will speak to the transport of radioactive waste in Ontario Power Generation. It will also mention non-waste shipments and the quality assurance programme used at Ontario Power Generation to ensure a high quality transportation system. (author)

  4. A flexible testing facility for high-power targets T-MIF

    International Nuclear Information System (INIS)

    Fusco, Y.; Samec, K.; Behzad, M.; Kadi, Y.

    2015-01-01

    A dedicated material test irradiation facility is being proposed. The testing station will allow critical issues concerning materials under irradiation to be addressed, such as the impact of proton beam irradiation, neutron irradiation, liquid metal corrosion and temperature. The material samples to be investigated in such a facility will be subjected to tensile stress, either constant or cyclical. The facility may also be used for sensor development under irradiation and isotope production. The goal of the current work is to propose a facility that is sufficiently versatile and compact so that it may be transported and used in different laboratories. The power is limited to 100 kW. The general aspect of the proposed irradiation facility is a cube, 2 metres deep and comprising within it all the necessary systems. The interface to the laboratory is limited to the coolant connections, the secondary circuit, the electric energy supply and the signals from the instrumentation. The liquid metal target placed in the centre of the facility contains the samples which are subjected to a proton beam, creating irradiation damage directly through protons or indirectly through neutrons created by spallation of the surrounding liquid metal by the incoming protons. The design of the target is based upon the EURISOL target. The same beam window design is used, albeit stretched horizontally to adopt an elliptical section which is compatible with the shape of the beam used to irradiate the samples. The liquid metal in the target is re-circulated by an electromagnetic pump that drives the liquid metal through a heat exchanger located at the top of the facility, the position of which was chosen to encourage natural circulation. The heat exchanger is made up of two separate parts which allow the primary and secondary circuit to separate cleanly

  5. Technology standards for structure, etc. concerning nuclear power generating facilities

    International Nuclear Information System (INIS)

    1977-01-01

    Based on the Ordinance for the Technology Standards concerning Nuclear Power Generating Facilities, the technology standards are established for the vessels of class 1 to 4 (including reactor pressure vessels, reactor containment vessels, etc.), the pipes of class 1 to 3, safety valves, pressure test and monitoring test specimens. Those specified are materials, nondestructive tests, structures, shapes, shells, flanges, etc. for the vessels and the pipes, and so on. (Mori, K.)

  6. Economic impacts of zebra mussels on drinking water treatment and electric power generation facilities.

    Science.gov (United States)

    Connelly, Nancy A; O'Neill, Charles R; Knuth, Barbara A; Brown, Tommy L

    2007-07-01

    Invasions of nonnative species such as zebra mussels can have both ecological and economic consequences. The economic impacts of zebra mussels have not been examined in detail since the mid-1990s. The purpose of this study was to quantify the annual and cumulative economic impact of zebra mussels on surface water-dependent drinking water treatment and electric power generation facilities (where previous research indicated the greatest impacts). The study time frame was from the first full year after discovery in North America (Lake St. Clair, 1989) to the present (2004); the study area was throughout the mussels' North American range. A mail survey resulted in a response rate of 31% for electric power companies and 41% for drinking water treatment plants. Telephone interviews with a sample of nonrespondents assessed nonresponse bias; only one difference was found and adjusted for. Over one-third (37%) of surveyed facilities reported finding zebra mussels in the facility and almost half (45%) have initiated preventive measures to prevent zebra mussels from entering the facility operations. Almost all surveyed facilities (91%) with zebra mussels have used control or mitigation alternatives to remove or control zebra mussels. We estimated that 36% of surveyed facilities experienced an economic impact. Expanding the sample to the population of the study area, we estimated 267 million dollars (BCa 95% CI = 161 million dollars - 467 million dollars) in total economic costs for electric generation and water treatment facilities through late 2004, since 1989. Annual costs were greater (44,000 dollars/facility) during the early years of zebra mussel infestation than in recent years (30,000 dollars). As a result of this and other factors, early predictions of the ultimate costs of the zebra mussel invasion may have been excessive.

  7. Power Systems Development Facility Gasification Test Campaing TC18

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2005-08-31

    In support of technology development to utilize coal for efficient, affordable, and environmentally clean power generation, the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama, routinely demonstrates gasification technologies using various types of coals. The PSDF is an engineering scale demonstration of key features of advanced coal-fired power systems, including a KBR Transport Gasifier, a hot gas particulate control device (PCD), advanced syngas cleanup systems, and high pressure solids handling systems. This report details Test Campaign TC18 of the PSDF gasification process. Test campaign TC18 began on June 23, 2005, and ended on August 22, 2005, with the gasifier train accumulating 1,342 hours of operation using Powder River Basin (PRB) subbituminous coal. Some of the testing conducted included commissioning of a new recycle syngas compressor for gasifier aeration, evaluation of PCD filter elements and failsafes, testing of gas cleanup technologies, and further evaluation of solids handling equipment. At the conclusion of TC18, the PSDF gasification process had been operated for more than 7,750 hours.

  8. Power Burst Facility: power oscillation problem

    International Nuclear Information System (INIS)

    Lussie, W.G.; Wadkins, R.P.; Wells, R.A.

    1975-01-01

    In late 1973 PBF achieved a power level of 15 MW. During this period of operation fluctuations in reactor power were observed. Many possible causes of these fluctuations were considered and a number of nuclear and non-nuclear tests were conducted. Initial instrumentation installed in the core showed coolant outlet temperature variations of 10 0 F for several fuel cannisters and approximately 10 percent power variations at 15 MW. Power spectral density analysis showed a predominant frequency of 0.05 to 0.06 HZ. The testing program to determine the cause of the power oscillations is described

  9. Locations and attributes of utility-scale solar power facilities in Colorado and New Mexico, 2011

    Science.gov (United States)

    Ignizio, Drew A.; Carr, Natasha B.

    2012-01-01

    The data series consists of polygonal boundaries for utility-scale solar power facilities (both photovoltaic and concentrating solar power) located within Colorado and New Mexico as of December 2011. Attributes captured for each facility include the following: facility name, size/production capacity (in MW), type of solar technology employed, location, state, operational status, year the facility came online, and source identification information. Facility locations and perimeters were derived from 1-meter true-color aerial photographs (2011) produced by the National Agriculture Imagery Program (NAIP); the photographs have a positional accuracy of about ±5 meters (accessed from the NAIP GIS service: http://gis.apfo.usda.gov/arcgis/services). Solar facility perimeters represent the full extent of each solar facility site, unless otherwise noted. When visible, linear features such as fences or road lines were used to delineate the full extent of the solar facility. All related equipment including buildings, power substations, and other associated infrastructure were included within the solar facility. If solar infrastructure was indistinguishable from adjacent infrastructure, or if solar panels were installed on existing building tops, only the solar collecting equipment was digitized. The "Polygon" field indicates whether the "equipment footprint" or the full "site outline" was digitized. The spatial accuracy of features that represent site perimeters or an equipment footprint is estimated at +/- 10 meters. Facilities under construction or not fully visible in the NAIP imagery at the time of digitization (December 2011) are represented by an approximate site outline based on the best available information and documenting materials. The spatial accuracy of these facilities cannot be estimated without more up-to-date imagery – users are advised to consult more recent imagery as it becomes available. The "Status" field provides information about the operational

  10. Conditioning and handling of tritiated wastes at Canadian nuclear power facilities

    International Nuclear Information System (INIS)

    Krochmalnek, L.S.; Krasznai, J.P.; Carney, M.

    1987-04-01

    Ontario Hydro operates a 10,000 MW capacity nuclear power system utilizing the CANDU pressurized heavy water reactor design. The use of D 2 O as moderator and coolant results in the production of about 2400 Ci of tritium per MWe-yr. As a result, there is significant Canadian experience in the treatment, handling, transport and storage of tritiated wastes. Ontario Hydro operates its own reactor waste storage site which includes systems for volume reduction, immobilization and packaging of wastes. In addition, a facility to remove tritium from heavy water is presently being commissioned at the Darlington nuclear site. This facility will generate tritiated liquid and solid waste that will have to be properly conditioned prior to storage or disposal. The nature of these various wastes and the processes/packaging required to meet storage/disposal criteria are judged to have relevance to investigations in fusion facility waste arisings. Experience to date, planned operational procedures and ongoing R and D in this area are described

  11. An environmental testing facility for Space Station Freedom power management and distribution hardware

    Science.gov (United States)

    Jackola, Arthur S.; Hartjen, Gary L.

    1992-01-01

    The plans for a new test facility, including new environmental test systems, which are presently under construction, and the major environmental Test Support Equipment (TSE) used therein are addressed. This all-new Rocketdyne facility will perform space simulation environmental tests on Power Management and Distribution (PMAD) hardware to Space Station Freedom (SSF) at the Engineering Model, Qualification Model, and Flight Model levels of fidelity. Testing will include Random Vibration in three axes - Thermal Vacuum, Thermal Cycling and Thermal Burn-in - as well as numerous electrical functional tests. The facility is designed to support a relatively high throughput of hardware under test, while maintaining the high standards required for a man-rated space program.

  12. Visibility and Visual Characteristics of the Ivanpah Solar Electric Generating System Power Tower Facility

    Energy Technology Data Exchange (ETDEWEB)

    Sullivan, Robert [Argonne National Lab. (ANL), Argonne, IL (United States); Abplanalp, Jennifer M. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2015-03-01

    This report presents the results of a study conducted to document the visibility and visual characteristics of the Ivanpah Solar Electric Generating System (ISEGS), a utility-scale solar power tower facility located on land administered by the U.S. Department of the Interior Bureau of Land Management in southern California. Study activities consisted of field observations of the ISEGS facility and comparison of the observations made in the field with the visual contrast assessments and visual simulations in the ISEGS Final Environmental Impact Statement (Final EIS) and supporting documents created prior to ISEGS construction. Field observations of ISEGS were made from 19 locations within 35 mi (56 km) of the facility in the course of one week in September 2014. The study results established that reflected sunlight from the receivers was the primary source of visual contrast from the operating ISEGS facility. The ISEGS facility was found to be a major source of visual contrast for all observations up to 20 mi (32 km), and was easily visible at 35 mi. Glare from individual heliostats was frequently visible, and often brighter than the reflected light from the receivers. Heliostat glare caused discomfort for one or more viewers at distances up to 20 mi. The ISEGS power blocks were brightly lit at night, and were conspicuous at the observation distance of approximately 6 mi (10 km). The facility is substantially brighter and is seen more clearly in the field than in photographs of the facility or in the prepared simulations, which were based on photographs. The simulations of the ISEGS facility in the Final EIS, which were evaluated as part of this study, sometimes lacked spatial accuracy and realism. The evaluated simulations generally under-represented the actual visual contrast from the project, and some of the contrast ratings in the Final EIS predicted substantially lower levels of visual contrast than were actually observed for the operating facility.

  13. Cooling and heating facility for nuclear power plant

    International Nuclear Information System (INIS)

    Kakuta, Atsuro

    1994-01-01

    The present invention concerns a cooling and heating facility for a nuclear power plant. Namely, a cooling water supply system supplies cooling water prepared by a refrigerator for cooling the inside of the plant. A warm water supply system supplies warm water having its temperature elevated by using an exhausted heat from a reactor water cleanup system. The facility comprises a heat pump-type refrigerator disposed in a cold water supply system for producing cold water and warm water, and warm water pipelines for connecting the refrigerator and the warm water supply system. With such a constitution, when the exhaust heat from the reactor water cleanup system can not be used, warm water prepared by the heat pump type refrigerator is supplied to the warm water supply system by way of the warm water pipelines. Accordingly, when the exhaust heat from the reactor water cleanup system can not be used such as upon inspection of the plant, a portion of the refrigerators in a not-operated state can be used for heating. Supply of boiler steams in the plant is no more necessary or extremely reduced. (I.S.)

  14. Development of protection system for power supply facilities in JT-60U P-NBI for long pulse operation

    International Nuclear Information System (INIS)

    Ohshima, Katsumi; Okano, Fuminori; Honda, Atsushi; Shinozaki, Shin-ichi; Usui, Katsutomi; Noto, Katsuya; Kawai, Mikito; Ikeda, Yoshitaka

    2007-06-01

    In the positive ion based NBI (P-NBI) system, we have developed a protection system to protect the power supply facilities from over load during long pulse operation. The protection system monitors the voltage (V) and current (I) in the power supply facilities, and calculates the parameters of V2t and I2t in real-time, where T is the pulse duration. It turns off the power supply facilities when V2t and I2t are beyond the critical values. After two development stages, we have completed the protection system using a package typed PLC (Programmable Logic Controller) which has a high expandability of multi-unit operation. Moreover, we have constructed a user-friendly system by using a SCADA (Supervisory Control and Data Acquisition) system. (author)

  15. Consideration of external events in the design of nuclear facilities other than nuclear power plants, with emphasis on earthquakes

    International Nuclear Information System (INIS)

    2003-03-01

    The design of nuclear facilities other than nuclear power plants in relation to external events is not a well harmonized practice around the world. Traditionally, the design of these facilities has either been left to the provisions collected in national building codes and other industrial codes not specifically intended for nuclear facilities, or it has been the subject of complex analyses of the type usually performed for nuclear power plants. The IAEA has recently started a programme of development of safety standards for such facilities. The need to define the appropriate safety requirements for nuclear installations prompted a generic review of siting and design approaches for these facilities in relation to external events. Therefore the assessment methods for siting and design were reviewed by the engineering community to provide the overall design of such facilities with the necessary reliability level. This report aims to provide guidelines for the assessment of the safety of nuclear facilities other than nuclear power plants in relation to external events through the application of simplified methods and procedures for their siting and design. The approach adopted is both simplified and conservative compared with that used for power reactors. It seeks to provide a rational balance for a suitable combination of sustainable effort in site investigations and refinement in design procedures, compatible with the assigned safety objectives. This publication is related to IAEA-TECDOC-348 'Earthquake Resistant Design of Nuclear Facilities with Limited Radioactive Inventory' (1985) which focused on the seismic design of nuclear facilities with limited radioactive inventory. After some 17 years, parts of IAEA-TECDOC-348 needed modification, as new operational data have become available from many facilities. In addition, sophisticated design methodologies are now more easily obtainable, and experts felt that the trade-off between sustainable investment in the

  16. Utilisation of real-scale renewable energy test facility for validation of generic wind turbine and wind power plant controller models

    DEFF Research Database (Denmark)

    Zeni, Lorenzo; Gevorgian, Vahan; Wallen, Robb

    2016-01-01

    This article presents an example of application of a modern test facility conceived for experiments regarding the integration of renewable energy in the power system. The capabilities of the test facility are used to validate dynamic simulation models of wind power plants and their controllers....... The models are based on standard and generic blocks. The successful validation of events related to the control of active power (control phenomena in...

  17. Occupational radiation exposure at commercial nuclear power reactors and other facilities 1992. Twenty-fifth annual report, Volume 14

    International Nuclear Information System (INIS)

    Raddatz, C.T.

    1993-12-01

    This report summarizes the occupational radiation exposure information that has been reported to the NRC's Radiation Exposure Information Reporting System (REIRS) by nuclear power facilities and certain other categories of NRC licensees during the years 1969 through 1992. The bulk of the data presented in the report was obtained from annual radiation exposure reports submitted in accordance with the requirements of 10CFR20.407 and the technical specifications of nuclear power plants. Data on workers terminating their employment at certain NRC licensed facilities were obtained from reports submitted pursuant to 10CFR20.408. The 1992 annual reports submitted by about 364 licensees indicated that approximately 204,365 individuals were monitored, 183,927 of whom were monitored by nuclear power facilities. They incurred an average individual dose of 0.16 rem (cSv) and an average measurable dose of about 0.30 (cSv). Termination radiation exposure reports were analyzed to reveal that about 74,566 individuals completed their employment with one or more of the 364 covered licensees during 1992. Some 71,846 of these individuals terminated from power reactor facilities, and about 9,724 of them were considered to be transient workers who received an average dose of 0.50 rem (cSv)

  18. Occupational radiation exposure at commercial nuclear power reactors and other facilities, 1993. Volume 15, Twenty-six annual report

    International Nuclear Information System (INIS)

    Raddatz, C.T.

    1995-01-01

    This report the occupational radiation exposure information that has been reported to the NRC's Radiation Exposure Information Reporting System (REIRS) by nuclear power facilities and certain other categories of NRC licensees during the years 1969 through 1993. The bulk of the data presented in the report was obtained from annual radiation exposure reports submitted in accordance with the requirements of 10 CFR 20.407 and the technical specifications of nuclear power plants. Data on workers terminating their employment at certain NRC licensed facilities were obtained from reports submitted pursuant to 10 CFR 20.408. The 1993 annual reports submitted by about 360 licensees indicated that approximately 189,711 individuals were monitored, 169,872 of whom were monitored by nuclear power facilities. They incurred an average individual dose of 0.16 rem (cSv) and an average measured dose of about 0.31 (cSv). Termination radiation exposure reports were analyzed to reveal that about 99,749 individuals completed their employment with one or more of the 360 covered licensees during 1993. Some 91,000 of these individuals terminated from power reactor facilities, and about 12,685 of them were considered to be transient workers who received an average dose of 0.49 rem (cSv)

  19. Power Burst Facility Severe Fuel Damage test series

    International Nuclear Information System (INIS)

    Buescher, B.J.; Osetek, D.J.; Ploger, S.A.

    1982-01-01

    The Severe Fuel Damage (SFD) tests planned for the Power Burst Facility (PBF) are described. Bundles containing 32 zircaloy-clad, PWR-type fuel rods will be subjected to severe overheating transients in a high-pressure, superheated-steam environment. Cladding temperatures are expected to reach 2400 0 K, resulting in cladding ballooning and rupture, severe cladding oxidation, cladding melting, fuel dissolution, fuel rod fragmentation, and possibly, rubble bed formation. An experiment effluent collection system is being installed and the PBF fission product monitoring system is being upgraded to meet the special requirements of the SFD tests. Scoping calculations were performed to evaluate performance of the SFD test design and to establish operational requirements for the PBF loop

  20. Reliability centred maintenance of nuclear power plant facilities

    International Nuclear Information System (INIS)

    Kovacs, Zoltan; Novakova, Helena; Hlavac, Pavol; Janicek, Frantisek

    2011-01-01

    A method for the optimization of preventive maintenance nuclear power plant equipment, i.e. reliability centred maintenance, is described. The method enables procedures and procedure schedules to be defined such as allow the maintenance cost to be minimized without compromising operational safety or reliability. Also, combinations of facilities which remain available and ensure reliable operation of the reactor unit during the maintenance of other pieces of equipment are identified. The condition-based maintenance concept is used in this process, thereby preventing unnecessary operator interventions into the equipment, which are often associated with human errors. Where probabilistic safety assessment is available, the most important structures, systems and components with the highest maintenance priority can be identified. (orig.)

  1. Current status of personnel exposure at nuclear power plants and other medical, industrial and educational facilities in JAPAN

    International Nuclear Information System (INIS)

    Sasaki, Fumiaki

    1991-01-01

    The state of radiation exposure of the workers engaging in radiation works in Japanese nuclear power stations, the factors of the radiation exposure of the workers engaging in radiation works, the countermeasures for reducing exposure in nuclear power stations, the state of radiation exposure of doctors, the workers engaging in radiation works, researchers and others in medical, industrial, research and educational and other facilities in Japan, the factors of their radiation exposure and the countermeasures for reducing the exposure, and the comparison of the exposure in nuclear power stations with that in medical, industrial, research and educational facilities are reported. (K.I.)

  2. 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.

  3. 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.

  4. Safety training and safe operating procedures written for PBFA (Particle Beam Fusion Accelerator) II and applicable to other pulsed power facilities

    Energy Technology Data Exchange (ETDEWEB)

    Donovan, G.L.; Goldstein, S.A.

    1986-12-01

    To ensure that work in advancing pulsed power technology is performed with an acceptably low risk, pulsed power research facilities at Sandia National Laboratories must satisfy general safety guidelines established by the Department of Energy, policies and formats of the Environment, Safety, and Health (ES and H) Department, and detailed procedures formulated by the Pulsed Power Sciences Directorate. The approach to safety training and to writing safe operating procedures, and the procedures presented here are specific to the Particle Beam Fusion Accelerator II (PBFA II) Facility but are applicable as guidelines to other research and development facilities which have similar hazards.

  5. Safety training and safe operating procedures written for PBFA [Particle Beam Fusion Accelerator] II and applicable to other pulsed power facilities

    International Nuclear Information System (INIS)

    Donovan, G.L.; Goldstein, S.A.

    1986-12-01

    To ensure that work in advancing pulsed power technology is performed with an acceptably low risk, pulsed power research facilities at Sandia National Laboratories must satisfy general safety guidelines established by the Department of Energy, policies and formats of the Environment, Safety, and Health (ES and H) Department, and detailed procedures formulated by the Pulsed Power Sciences Directorate. The approach to safety training and to writing safe operating procedures, and the procedures presented here are specific to the Particle Beam Fusion Accelerator II (PBFA II) Facility but are applicable as guidelines to other research and development facilities which have similar hazards

  6. Meson facility. Powerful new research tool

    International Nuclear Information System (INIS)

    Lobashev, V.M.; Tavkhelidze, A.N.

    A meson facility is being built at the Institute of Nuclear Research, USSR Academy of Sciences, in Troitsk, where the Scientific Center, USSR Academy of Sciences is located. The facility will include a linear accelerator for protons and negative hydrogen ions with 600 MeV energy and 0.5-1 mA beam current. Some fundamental studies that can be studied at a meson facility are described in the areas of elementary particles, neutron physics, solid state physics, and applied research. The characteristics of the linear accelerator are given and the meson facility's experimental complex is described

  7. International inventory of training facilities in nuclear power and its fuel cycle

    International Nuclear Information System (INIS)

    1977-01-01

    Because the development of trained manpower is important for full use of nuclear power, the International Atomic Energy Agency has compiled this first inventory of training facilities and programs. It is based on information submitted by Member States and received up to 31 January 1977. The inventory is arranged by country, type of training organization, and by subject

  8. Design considerations and analysis of potential applications of a high power ultraviolet FEL at the TESLA test facility at DESY

    International Nuclear Information System (INIS)

    Pagani, C.; Saldin, E.L.; Schneidmiller, E.A.; Yurkov, M.V.

    1999-01-01

    A possibility of constructing a high power ultraviolet free electron laser at the TESLA test facility at DESY is discussed. The proposed facility consists of a tunable master oscillator (P av ∼10 mW, P peak ∼10 kW, λ≅200-350 nm) and an FEL amplifier with a tapered undulator. The average and peak radiation power at the exit of the FEL amplifier is about 7 kW and 220 GW, respectively. Installation of such a facility can significantly extend scientific potential of the TESLA test facility. The UV free electron laser can be used to construct a polarized, monochromatic gamma-source with the ultimate yield up to 10 12 gamma-quanta per second and the maximal energy of about 100 MeV. An intensive gamma-source can also form the base for constructing the test facility for the TESLA positron generation system. Another accelerator application of the proposed facility is verification of the main technical solutions for the laser and the optical system to be used in the gamma-gamma option of the TESLA collider. A high average power UV laser is also promising for industrial applications

  9. Managing risks during the construction of a power generation facility

    International Nuclear Information System (INIS)

    Loulakis, M.C.

    1992-01-01

    The construction of a power generation facility is a substantial undertaking that involves considerable risks to all parties involved. While contractors are accustomed to dealing with risks, construction owners are typically more naive about not only the risks they are assuming in the construction of a project, but also about the role they play on the project itself. Owners and developers of power facilities must understand at the outset that their role during the construction of a project is as integral to the success of the project as that of the designer and contractor. In addition, owners should also understand that there are virtually no risks on a construction project that cannot be shifted among the contracting parties as part of the business deal. Consequently, an owner may contractually be assuming the risks of (1) unusually severe weather, (2) unexpected subsurface conditions, (3) strikes at the turbine supplier's plant or (4) changes in law - as well as the increases in price and delays to project completion associated with such risks. In light of this, a prudent owner will evaluate more than just whether there is sufficient financing to complete the construction of a contemplated project. Prudent owners will conduct a risk management review of the project structure and the contracting terms, with the primary focus being (1) the identification and analysis of the most significant risks faced, (2) a determination of how such risks can be either mitigated or eliminated, and (3) the assessment of the financial exposure to the owner should the potential risk become a reality. This paper will present the framework that owners and developers of power generation projects can use in undertaking such a risk management review

  10. A distributed process monitoring system for nuclear powered electrical generating facilities

    International Nuclear Information System (INIS)

    Sweney, A.D.

    1991-01-01

    Duke Power Company is one of the largest investor owned utilities in the United States, with a service area of 20,000 square miles extending across North and South Carolina. Oconee Nuclear Station, one of Duke Power's three nuclear generating facilities, is a three unit pressurized water reactor site and has, over the course of its 15-year operating lifetime, effectively run out of plant processing capability. From a severely overcrowded cable spread room to an aging overtaxed Operator Aid Computer, the problems with trying to add additional process variables to the present centralized Operator Aid Computer are almost insurmountable obstacles. This paper reports that for this reason, and to realize the inherent benefits of a distributed process monitoring and control system, Oconee has embarked on a project to demonstrate the ability of a distributed system to perform in the nuclear power plant environment

  11. Research on adoption of graphic processing system into electric power facilities operation management. Denryoku setsubi kanri gyomu ni okeru zukei shori system no tekiyo ni kansuru kenkyu

    Energy Technology Data Exchange (ETDEWEB)

    Jitsubuchi, Yoshiyasu; Uryu, Kenji; Terasaki, Naoaki (Kyushu Electric Power Co., Inc., Fukuoka (Japan))

    1989-03-30

    In the technical department of electric power companies, there are innumerable single line diagram, machinery arrangement plan and other facilities drawings. Based on those drawings, facilities planning, work design, construction plan, maintenance and management data, etc. are made, for which making heightening is desired in efficiency of drawing filing management. Therefore, research was made on the adoption of CAD technology through modeling power transmission line, and power generating and transforming station operation management. First for the application of power transmission facilities, the power transmission line plan and facilities information were planned to be unified in management. Ie., the power transmission line plan and profile being shown on the display, symbols of steel towers, cable lines, etc. were further picked by mouth to easily substantiate the facilities. While image input and CAD of drawing were made in combined treatment. Then for the application to the power generating and transforming facilities, the single line diagram and facilities information were unified in management, together with demonstration of data interchangeability among different kinds of CAD system. 13 figs., 9 tabs.

  12. Analysis of Opportunity to Create Self-Regulating Reactor Facility of Extra-Low Power

    International Nuclear Information System (INIS)

    Kazansky, Y.A.; Levtchenko, V.A.; Yuriev, Y.S.

    2002-01-01

    This paper deals with fundamental possibilities (economy, safety, self-regulation) of creating an extra-low power reactor facility for heat supply. It contains the results of calculations for thermal and fast neutron reactors. The concept of this type of a reactor had been developed by the contributors earlier

  13. Design Basis Provisions for New and Existing Nuclear Power Plants and Nuclear Fuel Cycle Facilities in India

    International Nuclear Information System (INIS)

    Soni, R.S.

    2013-01-01

    India has 3-Stage Nuclear Power Program. • Various facilities under design, construction or operation. • Design Basis Knowledge Management (DBKM) is an important and challenging task. • Design Basis Knowledge contributes towards: - Safe operation of running plants; - Design and construction of new facilities; - Addresses issues related to future decommissioning activities

  14. Defense waste processing facility at Savannah River Plant. Instrument and power jumpers

    International Nuclear Information System (INIS)

    Heckendorm, F.M. II.

    1983-06-01

    The Defense Waste Processing Facility (DWPF) for waste vitrification at the Savannah River Plant is in the final design stage. Development of equipment interconnecting devices or jumpers for use within the remotely operated processing canyon is now complete. These devices provide for the specialized instrument and electrical requirements of the DWPF process for low-voltage, high-frequency, and high-power interconnections

  15. State-of-the-art WEB -technologies and ecological safety of nuclear power engineering facilities

    International Nuclear Information System (INIS)

    Batij, V.G.; Batij, E.V.; Rud'ko, V.M.; Kotlyarov, V.T.

    2004-01-01

    Prospects of web-technologies using in the field of improvement radiation safety level of nuclear power engineering facilities is seen. It is shown that application of such technologies will enable entirely using the data of all information systems of radiation control

  16. The state of radioactive waste management and of personnel radiation exposure in nuclear power generating facilities in fiscal 1983

    International Nuclear Information System (INIS)

    1985-01-01

    (1) The state of radioactive waste management in nuclear power generating facilities: In the nuclear power stations, the released quantities of radioactive gaseous and liquid wastes are all below the control objective levels. For the respective nuclear power stations, the released quantities of radioactive gaseous and liquid wastes in fiscal 1983 and the objective levels are given in table. And, the quantities of solid wastes taken into storage and the cumulative amounts are given. For reference, the results each year since fiscal 1974 are shown. (2) The state of personnel radiation exposure in nuclear power generating facilities: In the nuclear power stations, the personnel radiation exposures are all below the permissible levels. The dose distribution etc. in the respective nuclear power stations are given in table. For reference, the results each year since fiscal 1974 are shown. (Mori, K.)

  17. Present state of inspection robot technology in nuclear power facilities. Case of fast breeder reactors

    International Nuclear Information System (INIS)

    Ara, Kuniaki

    1995-01-01

    In the maintenance works in nuclear power facilities such as checkup, inspection and repair, for the main purpose of radiation protection, remote operation technology was introduced since relatively early stage, and at present, the robots that carry out the inspection works for confirming the soundness of main equipment have been developed and put to practical use. At the time of introducing these technologies, in addition to the research and development of robots proper, the coordination with the design of plant machinery and equipment facilities as the premise of introducing robots is an important requirement. In this report, the present state of the development of remote inspection technology for fast breeder reactors is introduced, and the matters to which attention is paid in the plant design for introducing robots are explained. First, fast breeder reactors are described. The needs of robotizing and adopting remote operation in nuclear power facilities are explained, using the examples of the inspection system for a reactor vessel and the inspection system for steam generator heat transfer tubes. (K.I.)

  18. Report of third regular inspection of Tokai reprocessing facilities, Power Reactor and Nuclear Fuel Development Corp

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    The reprocessing facilities passed the inspection before use on December 25, 1980, and started the full operation. Since then, this is the third regular inspection. It was begun on April 1, 1986, and finished on August 18, 1986, with the inspection of the rate of recovery of products. The reprocessing facilities which became the object of inspection were the facilities for accepting and storing spent fuel, the reprocessing facilities proper (the facilities of shearing, dissolution, separation, refining, denitration and recovery of acid and solvent), the facilities for storing products, measurement and control system, radioactive waste facilities, radiation control facilities and attached facilities (power, water, steam and testing). The main works carried out during the period of this regular inspection were the repair of an enriched uranium dissolution tank by welding, the renewal of a piping for a low activity waste liquid storing tank, and the removal of a washing tank. The total exposure dose in the first half of fiscal year 1986 was about 30.81 man-rem. (Kako, I.)

  19. Soft x-ray power diagnostic improvements at the Omega Laser Facility

    International Nuclear Information System (INIS)

    Sorce, C.; Schein, J.; Weber, F.; Widmann, K.; Campbell, K.; Dewald, E.; Turner, R.; Landen, O.; Jacoby, K.; Torres, P.; Pellinen, D.

    2006-01-01

    Soft x-ray power diagnostics are essential for evaluating high temperature laser plasma experiments. The Dante soft x-ray spectrometer, a core diagnostic for radiation flux and temperature measurements of Hohlraums, installed on the Omega Laser Facility at the Laboratory for Laser Energetics has recently undergone a series of upgrades. Work performed at Brookhaven National Laboratory for the development of the National Ignition Facility (NIF) Dante spectrometer enables the Omega Dante to offer a total of 18 absolutely calibrated channels in the energy range from 50 eV to 20 keV. This feature provides Dante with the capability to measure higher, NIF relevant, radiation temperatures with increased accuracy including a differentiation of higher energy radiation such as the Au M and L bands. Diagnostic monitoring using experimental data from directly driven Au spherical shots is discussed

  20. Acoustic assessment report for Toronto Hydro Energy Services Inc. Ashbridge's Bay power generation facility

    International Nuclear Information System (INIS)

    Bernard, F.; Shinbin, N.

    2010-04-01

    This acoustic assessment report was conducted to determine the potential noise impacts of a biogas cogeneration plant that will be located on a street in a primarily industrial area of Toronto, Ontario. The facility will be comprised of seven 1.416 MW biogas-fired reciprocating engine generators and a single flare. The report presented results obtained from noise level calculations and noise modelling studies of the on-site equipment at the planned facility. The cogeneration plant will utilize biogas produced in existing digesters to generate electricity and hot water. The biogas will be produced by anaerobic digestion from municipal sewage waste at an adjacent facility. It is expected that the facility will generate 9.912 MW of electricity from the generators. Heat resulting from the biogas combustion process is recovered from engine and exhaust flue gases by heat exchangers. The facility will operate continuously. Significant noise sources at the facility include generator exhaust gas stacks; air intake points; building ventilation fans; and roof-top heat dump radiators. Sound power levels determined for each of the noise sources were based upon worst-case operating scenarios. Results of the assessment indicated that the facility is in compliance with all Ministry of the Environment (MOE) requirements. 5 refs., 10 tabs., 4 figs.

  1. Ground Shock Resistant of Buried Nuclear Power Plant Facility

    International Nuclear Information System (INIS)

    Ornai, D.; Adar, A.; Gal, E.

    2014-01-01

    Nuclear Power Plant (NPP) might be subjected to hostile attacks such as Earth Penetrating Weapons (EPW) that carry explosive charges. Explosions of these weapons near buried NPP facility might cause collapse, breaching, spalling, deflection, shear, rigid body motion (depending upon the foundations), and in-structure shock. The occupants and the equipment in the buried facilities are exposed to the in-structure motions, and if they are greater than their fragility values than occupants might be wounded or killed and the equipment might be damaged, unless protective measures will be applied. NPP critical equipment such as pumps are vital for the normal safe operation since it requires constant water circulation between the nuclear reactor and the cooling system, including in case of an immediate shut down. This paper presents analytical- semi empirical formulation and analysis of the explosion of a penetrating weapon with a warhead of 100kgs TNT (Trinitrotoluene) that creates ground shock effect on underground NPP structure containing equipment, such as a typical pump. If the in-structure spectral shock is greater than the pump fragility values than protective measures are required, otherwise a real danger to the NPP safety might occur

  2. Operation and utilization of low power research reactor critical facility for Advanced Heavy Water Reactor (AHWR)

    International Nuclear Information System (INIS)

    De, S.K.; Karhadkar, C.G.

    2017-01-01

    An Advanced Heavy Water Reactor (AHWR) has been designed and developed for maximum power generation from thorium considering large reserves of thorium. The design envisages using 54 pin MOX cluster with different enrichment of "2"3"3U and Pu in Thoria fuel pins. Theoretical models developed to neutron transport and the geometrical details of the reactor including all reactivity devices involve approximations in modelling, resulting in uncertainties. With a view to minimize these uncertainties, a low power research reactor Critical Facility was built in which cold clean fuel can be arranged in a desired and precise geometry. Different experiments conducted in this facility greatly contribute to understand and validate the physics design parameters

  3. Seismic experience in power and industrial facilities as it relates to small magnitude earthquakes

    International Nuclear Information System (INIS)

    Swan, S.W.; Horstman, N.G.

    1987-01-01

    The data base on the performance of power and industrial facilities in small magnitude earthquakes (M = 4.0 - 5.5) is potentially very large. In California alone many earthquakes in this magnitude range occur every year, often near industrial areas. In 1986 for example, in northern California alone, there were 76 earthquakes between Richter magnitude 4.0 and 5.5. Experience has shown that the effects of small magnitude earthquakes are seldom significant to well-engineered facilities. (The term well-engineered is here defined to include most modern industrial installations, as well as power plants and substations.) Therefore detailed investigations of small magnitude earthquakes are normally not considered worthwhile. The purpose of this paper is to review the tendency toward seismic damage of equipment installations representative of nuclear power plant safety systems. Estimates are made of the thresholds of seismic damage to certain types of equipment in terms of conventional means of measuring the damage potential of an earthquake. The objective is to define thresholds of damage that can be correlated with Richter magnitude. In this manner an earthquake magnitude might be chosen below which damage to nuclear plant safety systems is not considered credible

  4. Magnetohydrodynamics (MHD) Engineering Test Facility (ETF) 200 MWe power plant Conceptual Design Engineering Report (CDER)

    Science.gov (United States)

    1981-01-01

    The reference conceptual design of the magnetohydrodynamic (MHD) Engineering Test Facility (ETF), a prototype 200 MWe coal-fired electric generating plant designed to demonstrate the commercial feasibility of open cycle MHD, is summarized. Main elements of the design, systems, and plant facilities are illustrated. System design descriptions are included for closed cycle cooling water, industrial gas systems, fuel oil, boiler flue gas, coal management, seed management, slag management, plant industrial waste, fire service water, oxidant supply, MHD power ventilating

  5. Intervention in independent spent fuel storage facility license application proceedings for storage on the power plant site

    International Nuclear Information System (INIS)

    Jordan, J.

    1992-01-01

    This presentation summarizes the intervention in the Nuclear Regulatory Commission (NRC) licensing process for currently operating Independent Spent fuel Storage Installation (ISFSI) projects at Carolina Power and Light's Company's H.B. Robinson, Duke Power Company's Oconee, and Virginia Power Company's Surry. In addition, intervention at dry storage facilities that are currently under development are also described. The utilities and reactors include Baltimore Gas and Electric Company's Calvert Cliffs, Public Service Company of Colorado's Fort St. Vrain plant, Northern States Power Company's Prairie Island, Wisconsin Electric Power Company's Point Beach, and Consumers Power Company's Palisades

  6. High-power light-emitting diode based facility for plant cultivation

    Energy Technology Data Exchange (ETDEWEB)

    Tamulaitis, G [Institute of Materials Science and Applied Research, Vilnius University, Sauletekio al. 9-III, LT-10222 Vilnius (Lithuania); Duchovskis, P [Lithuanian Institute of Horticulture, Babtai, LT-54333 Kaunas District (Lithuania); Bliznikas, Z [Institute of Materials Science and Applied Research, Vilnius University, Sauletekio al. 9-III, LT-10222 Vilnius (Lithuania); Breive, K [Institute of Materials Science and Applied Research, Vilnius University, Sauletekio al. 9-III, LT-10222 Vilnius (Lithuania); Ulinskaite, R [Lithuanian Institute of Horticulture, Babtai, LT-54333 Kaunas District (Lithuania); Brazaityte, A [Lithuanian Institute of Horticulture, Babtai, LT-54333 Kaunas District (Lithuania); Novickovas, A [Institute of Materials Science and Applied Research, Vilnius University, Sauletekio al. 9-III, LT-10222 Vilnius (Lithuania); Zukauskas, A [Institute of Materials Science and Applied Research, Vilnius University, Sauletekio al. 9-III, LT-10222 Vilnius (Lithuania)

    2005-09-07

    Based on perspectives of the development of semiconductor materials systems for high-power light-emitting diodes (LEDs), an illumination facility for greenhouse plant cultivation was designed with the dominating 640 nm photosynthetically active component delivered by AlGaInP LEDs and supplementary components from AlGaN (photothropic action, 455 nm) and AlGaAs (photosynthetic 660 nm and photomorphogenetic 735 nm) LEDs. Photosynthesis intensity, photosynthetic productivity and growth morphology as well as chlorophyll and phytohormone concentrations were investigated in radish and lettuce grown in phytotron chambers under the LED-based illuminators and under high-pressure sodium (HPS) lamps with an equivalent photon flux density. Advantages of the high-power LED-based illuminators over conventional HPS lamps, applicability of AlGaInP LEDs for photosynthesis and control of plant growth by circadian manipulation of a relatively weak far-red component were demonstrated.

  7. High-power light-emitting diode based facility for plant cultivation

    International Nuclear Information System (INIS)

    Tamulaitis, G; Duchovskis, P; Bliznikas, Z; Breive, K; Ulinskaite, R; Brazaityte, A; Novickovas, A; Zukauskas, A

    2005-01-01

    Based on perspectives of the development of semiconductor materials systems for high-power light-emitting diodes (LEDs), an illumination facility for greenhouse plant cultivation was designed with the dominating 640 nm photosynthetically active component delivered by AlGaInP LEDs and supplementary components from AlGaN (photothropic action, 455 nm) and AlGaAs (photosynthetic 660 nm and photomorphogenetic 735 nm) LEDs. Photosynthesis intensity, photosynthetic productivity and growth morphology as well as chlorophyll and phytohormone concentrations were investigated in radish and lettuce grown in phytotron chambers under the LED-based illuminators and under high-pressure sodium (HPS) lamps with an equivalent photon flux density. Advantages of the high-power LED-based illuminators over conventional HPS lamps, applicability of AlGaInP LEDs for photosynthesis and control of plant growth by circadian manipulation of a relatively weak far-red component were demonstrated

  8. Power Systems Development Facility Gasification Test Run TC11

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2003-04-30

    This report discusses Test Campaign TC11 of the Kellogg Brown & Root, Inc. (KBR) Transport Gasifier train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Gasifier is an advanced circulating fluidized-bed gasifier designed to operate as either a combustor or a gasifier in air- or oxygen-blown mode of operation using a particulate control device (PCD). Test run TC11 began on April 7, 2003, with startup of the main air compressor and the lighting of the gasifier start-up burner. The Transport Gasifier operated until April 18, 2003, when a gasifier upset forced the termination of the test run. Over the course of the entire test run, gasifier temperatures varied between 1,650 and 1,800 F at pressures from 160 to 200 psig during air-blown operations and around 135 psig during enriched-air operations. Due to a restriction in the oxygen-fed lower mixing zone (LMZ), the majority of the test run featured air-blown operations.

  9. Laser peening applications for next generation of nuclear power facilities

    International Nuclear Information System (INIS)

    Rankin, J.; Truong, C.; Walter, M.; Chen, H.-L.; Hackel, L.

    2008-01-01

    Generation of electricity by nuclear power can assist in achieving goals of reduced greenhouse gas emissions. Increased safety and reliability are necessary attributes of any new nuclear power plants. High pressure, hot water and radiation contribute to operating environments where Stress Corrosion Cracking (SCC) and hydrogen embrittlement can lead to potential component failures. Desire for improved steam conversion efficiency pushes the fatigue stress limits of turbine blades and other rotating equipment. For nuclear reactor facilities now being designed and built and for the next generations of designs, laser peening could be incorporated to provide significant performance life to critical subsystems and components making them less susceptible to fatigue, SCC and radiation induced embrittlement. These types of components include steam turbine blades, hubs and bearings as well as reactor components including cladding material, housings, welded assemblies, fittings, pipes, flanges, vessel penetrations, nuclear waste storage canisters. Laser peening has proven to be a commercial success in aerospace applications and has recently been put into use for gas and steam turbine generators and light water reactors. An expanded role for this technology for the broader nuclear power industry would be a beneficial extension. (author)

  10. Radioactivity measuring and control method and the system for facility of nuclear power plant

    International Nuclear Information System (INIS)

    Urata, Megumu.

    1996-01-01

    In measurement and control for radioactivity in an inspection operation in radiation circumstance for nuclear power plant facilities, radioactive materials in air are sometimes suspended together with ordinary dusts. Then, when a radiation level is low, light is applied to the suspended dusts to measure the quantity and the number of the dusts thereby estimating the radiation level based on the amount of the dusts. Then, the level of the equipments is informed to an operator based on the estimated value, and an operation time is determined. Since the optical dust monitor is inexpensive, a number of dust monitors can be brought into an operation chamber. In addition, they are reduced in the size and the weight, an operator can carry and bring them into the operation chamber. A distribution of dusts can be determined by measuring the concentration of dusts using a plurality of dust monitors thereby enabling to improve safety and economical property of periodical inspection for nuclear power plant facilities. (T.M.)

  11. Radioactivity measuring and control method and the system for facility of nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Urata, Megumu

    1996-12-03

    In measurement and control for radioactivity in an inspection operation in radiation circumstance for nuclear power plant facilities, radioactive materials in air are sometimes suspended together with ordinary dusts. Then, when a radiation level is low, light is applied to the suspended dusts to measure the quantity and the number of the dusts thereby estimating the radiation level based on the amount of the dusts. Then, the level of the equipments is informed to an operator based on the estimated value, and an operation time is determined. Since the optical dust monitor is inexpensive, a number of dust monitors can be brought into an operation chamber. In addition, they are reduced in the size and the weight, an operator can carry and bring them into the operation chamber. A distribution of dusts can be determined by measuring the concentration of dusts using a plurality of dust monitors thereby enabling to improve safety and economical property of periodical inspection for nuclear power plant facilities. (T.M.)

  12. Facilities for the treatment of radioactively contaminated water in nuclear power plants

    International Nuclear Information System (INIS)

    1978-01-01

    The regulation is to be applied to design, construction and operation of facilities for the treatment of contaminated water in stationary nuclear power plants with LWR and HTR. The facilities are to be designed, constructed and operated in such manner that (a) imcontrolled discharge of contaminated water is avoided (Paragraph 46 section 1, no. 1 Radiation Protection Regulation) (b) the activity discharged with water is as low as possible ( paragraph 46, section 2, no. 2 Radiation Protection Regulation) (c)contaminated water will not get into the ground, unless this is permitted by a license (paragraph 46 section 6 Radiation Protection Regulation) (d) the radiation exposure resulting from direct radiation, contamination and inhalation of the personnel working with the facility is as low as possible and, at the most, corresponds to the values fixed in the regulation (paragraph 28 section 1 Radiation Protection Regulation) or the values given in the discharge permit. The regulation is not to be applied to installations for reactor coolant or fuel pit clean-up. (orig./HP) [de

  13. Culture-based Identification Of Microcystin-Degrading Bacteria In the Sandusky Bay and Maumee Bay of Lake Erie

    Science.gov (United States)

    Ormiston, A.; Mou, X.

    2012-12-01

    Harmful cyanobacteria blooms (cyanoHABs) are a serious issue that affects wildlife, human health, recreation and local economics worldwide. CyanoHABs produce cyanotoxins, such as microcystins (MCs) that lead to skin irritation, illness and liver tumors. Bacterially mediated degradation of MCs plays a key role to transform these toxic substrates to less harmful metabolites in natural environments. However, only a few Sphingomonos species have been isolated for degradation of MCs and many of which are from other habitats such as water plants. This project aims to isolate and identify bacteria that can degrade MC-LR and MC-RR, two major forms of MCs found during cyanoHABs in Lake Erie. Water samples were collected from the surface of Sandusky Bay and Maumee Bay of Lake Erie and immediately filtered through 3.0 -μm-pore-size membrane filters to obtain bacterioplankton fraction. The filtrates were amended with excessive inorganic nitrogen and phosphorus compounds and incubated in the dark for a week to purposely establish a carbon-limited condition. Afterwards, enrichment microcosms were established in flasks filled with pre-incubated bacterioplankton and single MC compounds (final concentration 10 μM). Once cell growth was confirmed by flow cytometry-based cell counting, bacterial cells in enriched microcosms were transferred onto solid surfaces, i.e., GFF filter and noble agar for colony isolation. Obtained single colonies were inoculated in defined liquid media with MCs as single carbon source. DNA was extracted from each purified isolate and analyzed by restriction fragment length polymorphism analysis (RFLP). A total of 18 different RFLP banding patterns were found, indicating MC-degrading bacteria may be heterogeneous in studied water samples. 16S rRNA genes of selected bacterial isolates were PCR amplified and sequenced for taxonomic identification. Our results demonstrated that MCs can be degraded by multiple bacterial species in Lake Erie. Future directions

  14. RF power source for the compact linear collider test facility (CTF3)

    CERN Document Server

    McMonagle, G; Brown, Peter; Carron, G; Hanni, R; Mourier, J; Rossat, G; Syratchev, I V; Tanner, L; Thorndahl, L

    2004-01-01

    The CERN CTF3 facility will test and demonstrate many vital components of CLIC (Compact Linear Collider). This paper describes the pulsed RF power source at 2998.55 MHz for the drive-beam accelerator (DBA), which produces a beam with an energy of 150 MeV and a current of 3.5 Amps. Where possible, existing equipment from the LEP preinjector, especially the modulators and klystrons, is being used and upgraded to achieve this goal. A high power RF pulse compression system is used at the output of each klystron, which requires sophisticated RF phase programming on the low level side to achieve the required RF pulse. In addition to the 3 GHz system two pulsed RF sources operating at 1.5 GHz are being built. The first is a wide-band, low power, travelling wave tube (TWT) for the subharmonic buncher (SHB) system that produces a train of "phase coded" subpulses as part of the injector scheme. The second is a high power narrow band system to produce 20 MW RF power to the 1.5 GHz RF deflectors in the delay loop situate...

  15. Governments' role in decommissioning nuclear power facilities

    International Nuclear Information System (INIS)

    Guindon, S.; Wendling, R.D.; Gordelier, S.; Soederberg, O.; Averous, J.; Orlando, D.

    2005-01-01

    Many nuclear power plants will reach the end of their operating lives over the next 20 years; some may be life-extended, others may not. This development will precipitate enhanced industrial and regulatory activities in the area of decommissioning. We are also witnessing in many countries a significant shift in the role of government itself: new pressures on governments, such as enhanced attention on environmental impact/mitigation and strategies to implement market-oriented approaches in a variety of sectors, including the energy sector are driving the public policy agenda. The paper will examine the range of policy issues, drawing from recent NEA studies on decommissioning policies and the recent NEA study on Government and Nuclear Energy and, strategies and costs, and other current trends and developments in the nuclear industry and in the nuclear policy fields. The paper will reflect on issues to be addressed during the conference and draw conclusions on the appropriate role of government in this area. Decommissioning policy is very specific and focused: it is not a high level policy/political issue in most instances and rarely gets the same attention as the issue surrounding the future of nuclear energy itself and public concerns regarding safety, waste and economics. One reason why decommissioning does not get the same attention as for example disposal of spent nuclear fuel might be the fact that technology is available for decommissioning, while technology for disposal of spent nuclear fuel is under development. High profile or not, it will remain an important issue for governments and industry alike particularly because of the cost and long lead times involved. In some instances, governments are the owners of the facilities to be decommissioned. In addition, decommissioning factors into issues surrounding the economics of nuclear energy and the sustainability of the nuclear option. Based on results of the Tarragona Seminar (Spain, September 2-4, 2003) and

  16. Emergency and backup power supplies at Department of Energy facilities: Augmented Evaluation Team -- Final report

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-01

    This report documents the results of the Defense Programs (DP) Augmented Evaluation Team (AET) review of emergency and backup power supplies (i.e., generator, uninterruptible power supply, and battery systems) at DP facilities. The review was conducted in response to concerns expressed by former Secretary of Energy James D. Watkins over the number of incidents where backup power sources failed to provide electrical power during tests or actual demands. The AET conducted a series of on-site reviews for the purpose of understanding the design, operation, maintenance, and safety significance of emergency and backup power (E&BP) supplies. The AET found that the quality of programs related to maintenance of backup power systems varies greatly among the sites visited, and often among facilities at the same site. No major safety issues were identified. However, there are areas where the AET believes the reliability of emergency and backup power systems can and should be improved. Recommendations for improving the performance of E&BP systems are provided in this report. The report also discusses progress made by Management and Operating (M&O) contractors to improve the reliability of backup sources used in safety significant applications. One area that requires further attention is the analysis and understanding of the safety implications of backup power equipment. This understanding is needed for proper graded-approach implementation of Department of Energy (DOE) Orders, and to help ensure that equipment important to the safety of DOE workers, the public, and the environment is identified, classified, recognized, and treated as such by designers, users, and maintainers. Another area considered important for improving E&BP system performance is the assignment of overall ownership responsibility and authority for ensuring that E&BP equipment performs adequately and that reliability and availability are maintained at acceptable levels.

  17. First evidence of grass carp recruitment in the Great Lakes Basin

    Science.gov (United States)

    Chapman, Duane C.; Davis, J. Jeremiah; Jenkins, Jill A.; Kocovsky, Patrick M.; Miner, Jeffrey G.; Farver, John; Jackson, P. Ryan

    2013-01-01

    We use aging techniques, ploidy analysis, and otolith microchemistry to assess whether four grass carp Ctenopharyngodon idella captured from the Sandusky River, Ohio were the result of natural reproduction within the Lake Erie Basin. All four fish were of age 1 +. Multiple lines of evidence indicate that these fish were not aquaculture-reared and that they were most likely the result of successful reproduction in the Sandusky River. First, at least two of the fish were diploid; diploid grass carp cannot legally be released in the Great Lakes Basin. Second, strontium:calcium (Sr:Ca) ratios were elevated in all four grass carp from the Sandusky River, with elevated Sr:Ca ratios throughout the otolith transect, compared to grass carp from Missouri and Arkansas ponds. This reflects the high Sr:Ca ratio of the Sandusky River, and indicates that these fish lived in a high-strontium environment throughout their entire lives. Third, Sandusky River fish were higher in Sr:Ca ratio variability than fish from ponds, reflecting the high but spatially and temporally variable strontium concentrations of southwestern Lake Erie tributaries, and not the stable environment of pond aquaculture. Fourth, Sr:Ca ratios in the grass carp from the Sandusky River were lower in their 2011 growth increment (a high water year) than the 2012 growth increment (a low water year), reflecting the observed inverse relationship between discharge and strontium concentration in these rivers. We conclude that these four grass carp captured from the Sandusky River are most likely the result of natural reproduction within the Lake Erie Basin.

  18. Facility Effluent Monitoring Plan for the 284-E and 284-W power plants

    International Nuclear Information System (INIS)

    Herman, D.R.

    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 every three years. The 284-E and 284-W Power Plants are coal-fired plants used to generate steam. Electricity is not generated at these facilities. The maximum production of steam is approximately 159 t (175 tons)/h at 101 kg (225 lb)/in 2 . Steam generated at these facilities is used in other process facilities (i. e., the B Plant, Plutonium-Uranium Extraction Plant, 242-A Evaporator) for heating and process operations. The functions or processes associated with these facilities do not have the potential to generate radioactive airborne effluents or radioactive liquid effluents, therefore, radiation monitoring equipment is not used on the discharge of these streams. The functions or processes associated with the production of steam result in the use, storage, management and disposal of hazardous materials

  19. Operational Performance and Improvements to the RF Power Sources for the Compact Linear Collider Test Facility (CTF3) at CERN

    CERN Document Server

    McMonagle, Gerard

    2006-01-01

    The CERN CTF3 facility is being used to test and demonstrate key technical issues for the CLIC (Compact Linear Collider) study. Pulsed RF power sources are essential elements in this test facility. Klystrons at S-band (29998.55 GHz), in conjunction with pulse compression systems, are used to power the Drive Beam Accelerator (DBA) to achieve an electron beam energy of 150 MeV. The L-Band RF system, includes broadband Travelling Wave Tubes (TWTs) for beam bunching with 'phase coded' sub pulses in the injector and a narrow band high power L-Band klystron powering the transverse 1.5GHz RF deflector in the Delay Loop immediately after the DBA. This paper describes these different systems and discusses their operational performance.

  20. Operational performance and improvements to the rf power sources for the Compact Linear Collider Test Facility (CTF3) at CERN

    CERN Document Server

    McMonagle, Gerard

    2006-01-01

    The CERN CTF3 facility is being used to test and demonstrate key technical issues for the CLIC (Compact Linear Collider) study. Pulsed RF power sources are essential elements in this test facility. Klystrons at S-band (29998.55 GHz), in conjunction with pulse compression systems, are used to power the Drive Beam Accelerator (DBA) to achieve an electron beam energy of 150 MeV. The L-Band RF system, includes broadband Travelling Wave Tubes (TWTs) for beam bunching with 'phase coded' sub pulses in the injector and a narrow band high power L-Band klystron powering the transverse 1.5 GHz RF deflector in the Delay Loop immediately after the DBA. This paper describes these different systems and discusses their operational performance.

  1. Research and design of pulsed switching power supply for deep tumor therapy facility with heavy ions accelerator in Lanzhou

    International Nuclear Information System (INIS)

    Shi Chunfeng; Zhao Jiang; Yan Hongbin; Wu Fengjun; Gao Daqing

    2012-01-01

    The pulsed switching power supply was developed for deep tumor therapy facility with heavy ions in cooler-storage-ring of the heavy ions research facility in Lanzhou (HIRFL-CSR). The control principle of the dual closed-loop scheme was described and the open-loop Bode diagrams were given. The results of simulation and prototype experiment show that the current error gets much smaller than that of the single closed-loop pulsed switching power supply. Moreover, the simulation and test results were analyzed, and the circuit configuration and dual closed-loop strategy selected are practicable. (authors)

  2. Testing of the Engineering Model Electrical Power Control Unit for the Fluids and Combustion Facility

    Science.gov (United States)

    Kimnach, Greg L.; Lebron, Ramon C.; Fox, David A.

    1999-01-01

    The John H. Glenn Research Center at Lewis Field (GRC) in Cleveland, OH and the Sundstrand Corporation in Rockford, IL have designed and developed an Engineering Model (EM) Electrical Power Control Unit (EPCU) for the Fluids Combustion Facility, (FCF) experiments to be flown on the International Space Station (ISS). The EPCU will be used as the power interface to the ISS power distribution system for the FCF's space experiments'test and telemetry hardware. Furthermore. it is proposed to be the common power interface for all experiments. The EPCU is a three kilowatt 12OVdc-to-28Vdc converter utilizing three independent Power Converter Units (PCUs), each rated at 1kWe (36Adc @ 28Vdc) which are paralleled and synchronized. Each converter may be fed from one of two ISS power channels. The 28Vdc loads are connected to the EPCU output via 48 solid-state and current-limiting switches, rated at 4Adc each. These switches may be paralleled to supply any given load up to the 108Adc normal operational limit of the paralleled converters. The EPCU was designed in this manner to maximize allocated-power utilization. to shed loads autonomously, to provide fault tolerance. and to provide a flexible power converter and control module to meet various ISS load demands. Tests of the EPCU in the Power Systems Facility testbed at GRC reveal that the overall converted-power efficiency, is approximately 89% with a nominal-input voltage of 12OVdc and a total load in the range of 4O% to 110% rated 28Vdc load. (The PCUs alone have an efficiency of approximately 94.5%). Furthermore, the EM unit passed all flight-qualification level (and beyond) vibration tests, passed ISS EMI (conducted, radiated. and susceptibility) requirements. successfully operated for extended periods in a thermal/vacuum chamber, was integrated with a proto-flight experiment and passed all stability and functional requirements.

  3. Decommissioning and decontamination of licensed reactor facilities and demonstration nuclear power plants

    International Nuclear Information System (INIS)

    Lear, G.; Erickson, P.B.

    1975-01-01

    Decommissioning of licensed reactors and demonstration nuclear power plants has been accomplished by mothballing (protective storage), entombment, and dismantling or a combination of these three. The alternative selected by a licensee seems to be primarily based on cost. A licensee must, however, show that the decommissioning process provides adequate protection of the health and safety of the public and no adverse impact on the environment. To date the NRC has approved each of the alternatives in the decommissioning of different facilities. The decommissioning of small research reactors has been accomplished primarily by dismantling. Licensed nuclear power plants, however, have been decommissioned primarily by being placed in a mothballed state in which they continue to retain a reactor license and the associated licensee responsibilities

  4. X-band rf power production and deceleration in the two-beam test stand of the Compact Linear Collider test facility

    Directory of Open Access Journals (Sweden)

    E. Adli

    2011-08-01

    Full Text Available We discuss X-band rf power production and deceleration in the two-beam test stand of the CLIC test facility at CERN. The rf power is extracted from an electron drive beam by a specially designed power extraction structure. In order to test the structures at high-power levels, part of the generated power is recirculated to an input port, thus allowing for increased deceleration and power levels within the structure. The degree of recirculation is controlled by a splitter and phase shifter. We present a model that describes the system and validate it with measurements over a wide range of parameters. Moreover, by correlating rf power measurements with the energy lost by the electron beam, as measured in a spectrometer placed after the power extraction structure, we are able to identify system parameters, including the form factor of the electron beam. The quality of the agreement between model and reality gives us confidence to extrapolate the results found in the present test facility towards the parameter regime of CLIC.

  5. X-band rf power production and deceleration in the two-beam test stand of the Compact Linear Collider test facility

    CERN Document Server

    Adli, E; Dubrovskiy, A; Syratchev, I; Ruber, R; Ziemann, V

    2011-01-01

    We discuss X-band rf power production and deceleration in the two-beam test stand of the CLIC test facility at CERN. The rf power is extracted from an electron drive beam by a specially designed power extraction structure. In order to test the structures at high-power levels, part of the generated power is recirculated to an input port, thus allowing for increased deceleration and power levels within the structure. The degree of recirculation is controlled by a splitter and phase shifter. We present a model that describes the system and validate it with measurements over a wide range of parameters. Moreover, by correlating rf power measurements with the energy lost by the electron beam, as measured in a spectrometer placed after the power extraction structure, we are able to identify system parameters, including the form factor of the electron beam. The quality of the agreement between model and reality gives us confidence to extrapolate the results found in the present test facility towards the parameter reg...

  6. A UV pre-ionized dual-wavelength short-pulse high-power CO{sub 2} laser facility for laser particle acceleration research

    Energy Technology Data Exchange (ETDEWEB)

    Ebrahim, N A; Mouris, J F; Davis, R W

    1994-12-01

    In this report we describe the Chalk River dual-wavelength, short-pulse, single-mode, high-power CO{sub 2} laser facility for research in laser particle acceleration and CANDU materials modifications. The facility is designed and built around UV-preionized transversely-excited atmospheric-pressure (TEA) Lumonics CO{sub 2} laser discharge modules. Peak focussed power densities of up to 2 x 10{sup 14} W/cm{sup 2} in 500 ps pulses have been obtained. (author). 10 refs., 9 figs.

  7. Operation reliability analysis of independent power plants of gas-transmission system distant production facilities

    Science.gov (United States)

    Piskunov, Maksim V.; Voytkov, Ivan S.; Vysokomornaya, Olga V.; Vysokomorny, Vladimir S.

    2015-01-01

    The new approach was developed to analyze the failure causes in operation of linear facilities independent power supply sources (mini-CHP-plants) of gas-transmission system in Eastern part of Russia. Triggering conditions of ceiling operation substance temperature at condenser output were determined with mathematical simulation use of unsteady heat and mass transfer processes in condenser of mini-CHP-plants. Under these conditions the failure probability in operation of independent power supply sources is increased. Influence of environmental factors (in particular, ambient temperature) as well as output electric capability values of power plant on mini-CHP-plant operation reliability was analyzed. Values of mean time to failure and power plant failure density during operation in different regions of Eastern Siberia and Far East of Russia were received with use of numerical simulation results of heat and mass transfer processes at operation substance condensation.

  8. Report on emergency electrical power supply systems for nuclear fuel cycle and reactor facilities security systems

    International Nuclear Information System (INIS)

    1977-01-01

    The report includes information that will be useful to those responsible for the planning, design and implementation of emergency electric power systems for physical security and special nuclear materials accountability systems. Basic considerations for establishing the system requirements for emergency electric power for security and accountability operations are presented. Methods of supplying emergency power that are available at present and methods predicted to be available in the future are discussed. The characteristics of capacity, cost, safety, reliability and environmental and physical facility considerations of emergency electric power techniques are presented. The report includes basic considerations for the development of a system concept and the preparation of a detailed system design

  9. Report on emergency electrical power supply systems for nuclear fuel cycle and reactor facilities security systems

    Energy Technology Data Exchange (ETDEWEB)

    1977-01-01

    The report includes information that will be useful to those responsible for the planning, design and implementation of emergency electric power systems for physical security and special nuclear materials accountability systems. Basic considerations for establishing the system requirements for emergency electric power for security and accountability operations are presented. Methods of supplying emergency power that are available at present and methods predicted to be available in the future are discussed. The characteristics of capacity, cost, safety, reliability and environmental and physical facility considerations of emergency electric power techniques are presented. The report includes basic considerations for the development of a system concept and the preparation of a detailed system design.

  10. Operational Performance and Improvements to the RF Power Sources for the Compact Linear Collider Test Facility (CTF3) at CERN

    OpenAIRE

    McMonagle, Gerard

    2006-01-01

    The CERN CTF3 facility is being used to test and demonstrate key technical issues for the CLIC (Compact Linear Collider) study. Pulsed RF power sources are essential elements in this test facility. Klystrons at S-band (29998.55 GHz), in conjunction with pulse compression systems, are used to power the Drive Beam Accelerator (DBA) to achieve an electron beam energy of 150 MeV. The L-Band RF system, includes broadband Travelling Wave Tubes (TWTs) for beam bunching with 'phase coded' sub pulses ...

  11. Treatment of measurement uncertainties at the power burst facility

    International Nuclear Information System (INIS)

    Meyer, L.C.

    1980-01-01

    The treatment of measurement uncertainty at the Power Burst Facility provides a means of improving data integrity as well as meeting standard practice reporting requirements. This is accomplished by performing the uncertainty analysis in two parts, test independent uncertainty analysis and test dependent uncertainty analysis. The test independent uncertainty analysis is performed on instrumentation used repeatedly from one test to the next, and does not have to be repeated for each test except for improved or new types of instruments. A test dependent uncertainty analysis is performed on each test based on the test independent uncertainties modified as required by test specifications, experiment fixture design, and historical performance of instruments on similar tests. The methodology for performing uncertainty analysis based on the National Bureau of Standards method is reviewed with examples applied to nuclear instrumentation

  12. Detailed description of an SSAC at the facility level for light water moderated (off-load refueled) power reactor facilities

    International Nuclear Information System (INIS)

    Jones, R.J.

    1985-03-01

    This report is intended to provide the technical details of an effective State Systems of Accounting for and Control of Nuclear Material (SSAC) which Member States may use, if they wish, to establish and maintain their SSACs. It is expected that systems designed along the lines described would be effective in meeting the objectives of both national and international systems for nuclear material accounting and control. This document accordingly provides a detailed description of a system for the accounting for and control of nuclear material in an off-load refueled light water moderated power reactor facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

  13. Facilities and medical care for on-site nuclear power plant radiological emergencies

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    The operation of a nuclear power plant introduces risks of injury or accidents that could also result in the exposure of personnel to radiation or radioactive materials. It is important in such an event to have adequate first aid and medical facilities, supplies, equipment, transportation capabilities and trained personnel available to provide necessary care. This standard provides guidance for first aid during an emergency and for initial medical care of those overexposed to penetrating radiation or contaminated with radioactive material or radionuclides. Recommendations cover facilities, supplies, equipment and the extent of care on-site, where first aid and initial care may be provided, and off-site at a local hospital, where further medical and surgical care may be provided. Additional recommendations are also provided for the transportation of patients and the training of personnel. A brief discussion of specialized care is provided in an appendix

  14. Several new thermo-hydraulic test facilities in NPIC

    International Nuclear Information System (INIS)

    Ye Shurong; Sun Yufa; Ji Fuyun; Zong Guifang; Guo Zhongchuan

    1997-01-01

    Several new thermo-hydraulic test facilities are under construction in Nuclear Power Institute of Chinese (NPIC) at Chengdu. These facilities include: 1. Nuclear Power Component Comprehensive Test Facility. 2. Reactor Hydraulic Modeling Test Facility. 3. Control Rod Drive Line Hydraulic Test Facility. 4. Large Scale Thermo-Hydraulic Test Facility. The construction of these facilities will make huge progress in the research and development capability of nuclear power technology in CHINA. The author will present a brief description of the design parameters flowchart and test program of these facilities

  15. Power Systems Development Facility Gasification Test Campaign TC25

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2008-12-01

    In support of technology development to utilize coal for efficient, affordable, and environmentally clean power generation, the Power Systems Development Facility (PSDF), located in Wilsonville, Alabama, routinely demonstrates gasification technologies using various types of coals. The PSDF is an engineering scale demonstration of key features of advanced coal-fired power systems, including a KBR Transport Gasifier, a hot gas particulate control device, advanced syngas cleanup systems, and high-pressure solids handling systems. This report summarizes the results of TC25, the second test campaign using a high moisture lignite coal from the Red Hills mine in Mississippi as the feedstock in the modified Transport Gasifier configuration. TC25 was conducted from July 4, 2008, through August 12, 2008. During TC25, the PSDF gasification process operated for 742 hours in air-blown gasification mode. Operation with the Mississippi lignite was significantly improved in TC25 compared to the previous test (TC22) with this fuel due to the addition of a fluid bed coal dryer. The new dryer was installed to dry coals with very high moisture contents for reliable coal feeding. The TC25 test campaign demonstrated steady operation with high carbon conversion and optimized performance of the coal handling and gasifier systems. Operation during TC25 provided the opportunity for further testing of instrumentation enhancements, hot gas filter materials, and advanced syngas cleanup technologies. The PSDF site was also made available for testing of the National Energy Technology Laboratory's fuel cell module and Media Process Technology's hydrogen selective membrane with syngas from the Transport Gasifier.

  16. The national carbon capture center at the power systems development facility

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2012-09-01

    The Power Systems Development Facility (PSDF) is a state-of-the-art test center sponsored by the U.S. Department of Energy and dedicated to the advancement of clean coal technology. In addition to the development of advanced coal gasification processes, the PSDF features the National Carbon Capture Center (NCCC) to study CO2 capture from coal-derived syngas and flue gas. The NCCC includes multiple, adaptable test skids that allow technology development of CO2 capture concepts using coal-derived syngas and flue gas in industrial settings. Because of the ability to operate under a wide range of flow rates and process conditions, research at the NCCC can effectively evaluate technologies at various levels of maturity. During the Budget Period Three reporting period, efforts at the NCCC/PSDF focused on testing of pre-combustion CO2 capture and related processes; commissioning and initial testing at the post-combustion CO2 capture facilities; and operating the gasification process to develop gasification related technologies and for syngas generation to test syngas conditioning technologies.

  17. THE NATIONAL CARBON CAPTURE CENTER AT THE POWER SYSTEMS DEVELOPMENT FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2011-05-11

    The Power Systems Development Facility (PSDF) is a state-of-the-art test center sponsored by the U.S. Department of Energy and dedicated to the advancement of clean coal technology. In addition to the development of advanced coal gasification processes, the PSDF features the National Carbon Capture Center (NCCC) to study CO2 capture from coal-derived syngas and flue gas. The NCCC includes multiple, adaptable test skids that allow technology development of CO2 capture concepts using coal-derived syngas and flue gas in industrial settings. Because of the ability to operate under a wide range of flow rates and process conditions, research at the NCCC can effectively evaluate technologies at various levels of maturity. During the Budget Period Two reporting period, efforts at the PSDF/NCCC focused on new technology assessment and test planning; designing and constructing post-combustion CO2 capture facilities; testing of pre-combustion CO2 capture and related processes; and operating the gasification process to develop gasification related technologies and for syngas generation to test syngas conditioning technologies.

  18. Power Systems Development Facility Gasification Test Run TC09

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2002-09-30

    This report discusses Test Campaign TC09 of the Kellogg Brown & Root, Inc. (KBR) Transport Gasifier train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Gasifier is an advanced circulating fluidized-bed gasifier designed to operate as either a combustor or a gasifier in air- or oxygen-blown mode of operation using a particulate control device (PCD). The Transport Gasifier was operated as a pressurized gasifier during TC09 in air- and oxygen-blown modes. Test Run TC09 was started on September 3, 2002, and completed on September 26, 2002. Both gasifier and PCD operations were stable during the test run, with a stable baseline pressure drop. The oxygen feed supply system worked well and the transition from air to oxygen was smooth. The gasifier temperature varied between 1,725 and 1,825 F at pressures from 125 to 270 psig. The gasifier operates at lower pressure during oxygen-blown mode due to the supply pressure of the oxygen system. In TC09, 414 hours of solid circulation and over 300 hours of coal feed were attained with almost 80 hours of pure oxygen feed.

  19. Simulation of power maneuvering experiment of MASLWR test facility by MARS-KS code

    Energy Technology Data Exchange (ETDEWEB)

    Park, Ju Yeop [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2013-10-15

    In this ICSP, experimental data obtained from MASLWR (Mulit-Application Small Light Water Reactor) test facility located at Oregon state university in the US have been simulated by various thermal-hydraulic codes of each participant of the ICSP and compared among others. MASLWR test facility is a mock-up of a passive integral type reactor equipped with helical coil steam generator. Since SMART reactor which is currently being developed in Korea also adopts a helical coil steam generator, Korea Institute of Nuclear Safety (KINS) has joined this ICSP to assess the applicability of a domestic regulatory audit thermal-hydraulic code (i. e. MARS-KS code) for the SMART reactor including wall-to-fluid heat transfer model modification based on independent international experiment data. In the ICSP, two types of transient experiments have been focused and they are 1) loss of feedwater transient with subsequent ADS operation and long term cooling (SP-2) and normal operating conditions at different power levels. In the present study, KINS simulation result by the MARS-KS code (KS-002 version) for the SP-3 experiment is presented in detail and conclusion on MARS-KS code performance drawn through this simulation is described. Performance of the MARS-KS code is evaluated through the simulation of the power maneuvering experiment of the MASLWR test facility. Steady run shows the helical coil specific heat transfer model of the code is reasonable. However, identified discrepancy of the primary mass flowrate at transient run shows code performance for pressure drop needs to be improved considering sensitivity of the flowrate to the pressure drop at natural circulation.

  20. Change in plan for installation of nuclear reactor in Genkai Nuclear Power Plant of Kyushu Electric Power Co., Inc. (change in plan for No.3 and No.4 nuclear reactor facilities) (report)

    International Nuclear Information System (INIS)

    1987-01-01

    This report, compiled by the Nuclear Safety Commission to be submitted to the Minister of International Trade and Industry, deals with studies on a proposed change in the plan for the installation of nuclear reactors in the Genkai Nuclear Power Plant of Kyushu Electric Power Co., Inc. (change in the plan for the No.3 and No.4 nuclear reactor facilities). The conclusions of and principles for the examination and evaluation are described first. The studies carried out are focused on the safety of the facilities, and it is concluded that part of the proposed change is appropriate with respect to the required technical capability and that part of the change will not have adverse effects on the safety design of the facilities. The examination of the safety design of the reactor facilities cover the reactivity control, new material for the steam generator, design of chemical and volume control systems, design of liquid waste treatment facilities, integration of all confinement vessel spray rings, and design of the diesel power generator. It is confirmed that all of them can meet the safety requirements. Studies and analyses are also made of the emission of radiations to the surrounding environment, abnormal transient changes during operations, and possible accidents. (Nogami, K.)

  1. Power Burst Reactor Facility as an epithermal neutron source for brain cancer therapy

    International Nuclear Information System (INIS)

    Wheeler, F.J.

    1986-01-01

    The Power Burst Facility (PBF) reactor is considered for modification to provide an intense, clean source of intermediate-energy (epithermal) neutrons desirable for clinical studies of neutron capture therapy (NCT) for malignant tumors. The modifications include partial replacement of the reflector, installation of a neutron-moderating, shifting region, additional shielding, and penetration of the present concrete shield with a collimating (and optionally) filtering region. The studies have indicated that the reactor, after these modifications, will be safely operable at full power (28 MW) within the acceptable limits of the plant protection systems. The neutron beam exiting from the collimator port is predicted to be of sufficient intensity (approx.10 10 neutrons/cm 2 -s) to provide therapeutic doses in very short irradiation times. The beam would be relatively free of undesirable fast neutrons, thermal neutrons and gamma rays. The calculated neutron energy spectrum and associated gamma rays in the beam were provided as input in simulation studies that used a computer model of a patient with a brain tumor to determine predicted dose rates to the tumor and healthy tissue. The results of this conceptual study indicate an intense, clean beam of epithermal neutrons for NCT clinical trials is attainable in the PBF facility with properly engineered design modifications. 9 refs., 11 figs., 3 tabs

  2. A flexible testing facility for high-power targets (Tiara FP7 program)

    CERN Document Server

    Fusco, Y.; Samec, K.; Kadi, Y.

    2014-01-01

    Building on recent experience in the field of applied physics, TIARA Work package n° 9 focuses on target applications for accelerators in Europe. A roadmap for target development has been derived from major achievements in the EU-FP6 and EU-FP7 programs such as the MEGAPIE and EURISOL experiments. The TIARA management board concluded that a worthwhile continuation of such projects would be in the development of a flexible material irradiation facility easily transportable and which could be installed in different laboratories. The power is limited to 100 kW in a very compact arrangement so as to obtain the best neutron economy from a moderate beam power which is more likely to be found in laboratories across Europe. The challenges posed by such a compact design and accompanying calculations are presented in the current work.

  3. Reliability analysis for power supply system in a reprocessing facility based on GO methodology

    International Nuclear Information System (INIS)

    Wang Renze

    2014-01-01

    GO methodology was applied to analyze the reliability of power supply system in a typical reprocessing facility. Based on the fact that tie breakers are set in the system, tie breaker operator was defined. Then GO methodology modeling and quantitative analysis were performed sequently, minimal cut sets and average unavailability of the system were obtained. Parallel analysis between GO methodology and fault tree methodology was also performed. The results showed that setup of tie breakers was rational and necessary and that the modeling was much easier and the chart was much more succinct for GO methodology parallel with fault tree methodology to analyze the reliability of the power supply system. (author)

  4. Magnetohydrodynamics (MHD) Engineering Test Facility (ETF) 200 MWe power plant. Conceptual Design Engineering Report (CDER). Volume 2: Engineering. Volume 3: Costs and schedules

    Science.gov (United States)

    1981-01-01

    Engineering design details for the principal systems, system operating modes, site facilities, and structures of an engineering test facility (ETF) of a 200 MWE power plant are presented. The ETF resembles a coal-fired steam power plant in many ways. It is analogous to a conventional plant which has had the coal combustor replaced with the MHD power train. Most of the ETF components are conventional. They can, however, be sized or configured differently or perform additional functions from those in a conventional coal power plant. The boiler not only generates steam, but also performs the functions of heating the MHD oxidant, recovering seed, and controlling emissions.

  5. Feasibility Assessment of Using Power Plant Waste Heat in Large Scale Horticulture Facility Energy Supply Systems

    Directory of Open Access Journals (Sweden)

    Min Gyung Yu

    2016-02-01

    Full Text Available Recently, the Korean government has been carrying out projects to construct several large scale horticulture facilities. However, it is difficult for an energy supply to operate stably and economically with only a conventional fossil fuel boiler system. For this reason, several unused energy sources have become attractive and it was found that power plant waste heat has the greatest potential for application in this scenario. In this study, we performed a feasibility assessment of power plant waste heat as an energy source for horticulture facilities. As a result, it was confirmed that there was a sufficient amount of energy potential for the use of waste heat to supply energy to the assumed area. In Dangjin, an horticultural area of 500 ha could be constructed by utilizing 20% of the energy reserves. In Hadong, a horticulture facility can be set up to be 260 ha with 7.4% of the energy reserves. In Youngdong, an assumed area of 65 ha could be built utilizing about 19% of the energy reserves. Furthermore, the payback period was calculated in order to evaluate the economic feasibility compared with a conventional system. The initial investment costs can be recovered by the approximately 83% reduction in the annual operating costs.

  6. Evaluation of nuclear facility decommissioning projects. Status report. Humboldt Bay Power Plant Unit 3, SAFSTOR decommissioning

    International Nuclear Information System (INIS)

    Baumann, B.L.; Haffner, D.R.; Miller, R.L.; Scotti, K.S.

    1986-06-01

    This document explains the purpose of the US Nuclear Regulatory Commission's (NRC) Evaluation of Nuclear Facility Decommissioning Projects (ENFDP) program and summarizes information concerning the decommissioning of the Humboldt Bay Power Plant (HBPP) Unit 3 facility. Preparations to put this facility into a custodial safe storage (SAFSTOR) mode are currently scheduled for completion by June 30, 1986. This report gives the status of activities as of June 1985. A final summary report will be issued after completion of this SAFSTOR decommissioning activity. Information included in this status report has been collected from the facility decommissioning plan, environmental report, and other sources made available by the licensee. This data has been placed in a computerized data base system which permits data manipulation and summarization. A description of the computer reports that can be generated by the decommissioning data system (DDS) for Humboldt Bay and samples of those reports are included in this document

  7. Advanced Education Facilities for Power Electronics and Renewable Energy Systems at Aalborg University

    DEFF Research Database (Denmark)

    Teodorescu, Remus; Lungeanu, Marian; Blaabjerg, Frede

    2005-01-01

    A new approach for the project- and problem-based learning method is achieved at Aalborg University. Two new laboratories called Flexible Drives System Laboratory (FDSL) and Green Power Laboratory (GPL) have been developed. A common feature is that these facilities are using entirely Simulink for...... for programming, a very user-friendly block-oriented tool for designing control and different setups have been realized for practical implementation. Both the hardware and the course content is described in this paper....

  8. 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

  9. Active seismic response control systems for nuclear power plant equipment facilities

    International Nuclear Information System (INIS)

    Kobori, Takuji; Kanayama, Hiroo; Kamagata, Shuichi

    1989-01-01

    To sustain severe earthquake ground motion, a new type of anti-seismic structure is proposed, called a Dynamic Intelligent Building (DIB) system, which is positioned as an active seismic response controlled the structure. The structural concept starts from a new recognition of earthquake ground motion, and the structural natural frequency is actively adjusted to avoid resonant vibration, and similarly the external counter-force cancels the resonant force which comes from the dynamic structural motion energy. These concepts are verified using an analytical simulator program. The advanced application of the DIB system, is the Active Supporting system and the Active Stabilizer system for nuclear power plant equipment facilities. (orig.)

  10. Simulation of power maneuvering experiment of MASLWR test facility by MARS-KS code

    Energy Technology Data Exchange (ETDEWEB)

    Park, Ju Yeop [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2013-10-15

    In the present study, KINS simulation result by the MARS-KS code (KS-002 version) for the SP-3 experiment is presented in detail and conclusion on MARS-KS code performance drawn through this simulation is described. Performance of the MARS-KS code is evaluated through the simulation of the power maneuvering experiment of the MASLWR test facility. Steady run shows the helical coil specific heat transfer model of the code is reasonable. However, identified discrepancy of the primary mass flowrate at transient run shows code performance for pressure drop needs to be improved considering sensitivity of the flowrate to the pressure drop at natural circulation. Since 2009, IAEA has conducted a research program entitled as ICSP (International Collaborative Standard Problem) on integral PWR design to evaluate current the state of the art of thermal-hydraulic code in simulating natural circulation flow within integral type reactor. In this ICSP, experimental data obtained from MASLWR (Multi-Application Small Light Water Reactor) test facility located at Oregon state university in the US have been simulated by various thermal-hydraulic codes of each participant of the ICSP and compared among others. MASLWR test facility is a mock-up of a passive integral type reactor equipped with helical coil steam generator. Since SMART reactor which is currently being developed in Korea also adopts a helical coil steam generator, Korea Institute of Nuclear Safety (KINS) has joined this ICSP to assess the applicability of a domestic regulatory audit thermal-hydraulic code (i. e. MARS-KS code) for the SMART reactor including wall-to-fluid heat transfer model modification based on independent international experiment data. In the ICSP, two types of transient experiments have been focused and they are loss of feedwater transient with subsequent ADS operation and long term cooling (SP-2) and normal operating conditions at different power levels (SP-3)

  11. Siting locally-unwanted facilities: What can be learnt from the location of Italian power plants

    International Nuclear Information System (INIS)

    Garrone, Paola; Groppi, Angelamaria

    2012-01-01

    The reaction of communities to the development of energy facilities is based on the environmental impact of the investment, but it also reflects the ex-ante propensity of residents to engage in collective actions. In this work we have examined the requests of authorization of Italian power producers for new thermal plants with the purpose of testing the efficiency of market-based siting policies. The classical location factors, e.g., infrastructure availability, have been confirmed to play a role, and there is a weak evidence that authorization demands have targeted communities that suffer less environmental damage. However our findings have also revealed that power producers are likely to avoid potentially suitable sites if they host a highly activistic community. The paper also discusses some modifications concerning siting policies that could improve the alignment between community responses and the environmental costs of new energy facilities. - Highlights: ► We model location choices for polluting power plants by Italian producers in 1999–2006. ► The efficiency of market-based siting policies is tested (i.e., plants located where environmental damage is lower). ► More than environmental costs, voice factors prevailed on the location choices. ► We conclude that market-based siting policies does not ensure an efficient outcome. ► Developers and communities relationship may suffer from relevant transaction costs

  12. SUPER-CAPACITOR APPLICATION IN ELECTRICAL POWER CABLE TESTING FACILITIES IN THERMAL ENDURANCE AND MECHANICAL BRACING TESTS

    Directory of Open Access Journals (Sweden)

    I. V. Oleksyuk

    2015-01-01

    Full Text Available The current-carrying cores of the electrical power cables should be resistant to effects of short-circuit currents whose values depend on the material of the core, its cross-sectional area, cable insulation properties, environment temperature, and the duration of the short-circuit current flow (1 and 3–4 sec. when tested for thermal endurance and mechanical bracing. The facilities for testing the 10 kV aluminum core cables with short-circuit current shall provide mechanical-bracing current 56,82 kA and thermal endurance current 11,16 kA. Although capacitors provide such values of the testing currents to the best advantage, utilizing conventional capacitor-units will involve large expenditures for erecting and  running a separate building. It is expedient to apply super-capacitors qua the electric power supply for testing facilities, as they are capacitors with double-electrical layer and involve the current values of tens of kilo-amperes.The insulation voltage during short-circuit current testing being not-standardized, it is not banned to apply voltages less than 10 kV when performing short-circuit thermal endurance and mechanical bracing tests for electrical power cables of 10 kV. The super-capacitor voltage variation-in-time graph consists of two regions: capacitive and resistive. The capacitive part corresponds to the voltage change consequent on the energy change in the super-capacitors. The resistive part shows the voltage variation due to the active resistance presence in the super-capacitor.The author offers the algorithm determining the number of super capacitors requisite for testing 10 kV-electrical power cables with short-circuit currents for thermal endurance and mechanical bracing. The paper shows that installation of super-capacitors in the facilities testing the cables with short-circuit currents reduces the area needed for the super-capacitors in comparison with conventional capacitors more than by one order of magnitude.

  13. Results of special security inspection on improvement of security management setup in Head Office and Tsuruga Nuclear Power Station of the Japan Atomic Power Company and improvement of facilities in Tsuruga Nuclear Power Station

    International Nuclear Information System (INIS)

    1982-01-01

    In connection with the series of accidents in the Tsuruga Nuclear Power Station, the Agency of Natural Resources and Energy had instructed JAPC to make comprehensive inspection on the security management setup and to take improvement measures in the nuclear power station. The results of the subsequent inspection by ANRE confirmed that the improvements made by JAPC are adequate, and the following items are described: improvement of security management setup - communication and reporting in emergency, the management of inspection and maintenance records, work control and supervision in repair, improvement, etc., functional authority and responsibility in maintenance management, operation management, radiation control, personnel education; improvement of facilities - feed water heaters, laundry waste-water filter room, radioactive waste treatment facility, general drainage, concentrated waste liquid storage tanks in newly-built waste treatment building, etc. (J.P.N.)

  14. Design and construction of solidification and dewatering facility at Alabama Power Company's Farley Nuclear Plant

    International Nuclear Information System (INIS)

    Farnsworth, P.

    1988-01-01

    The approximate total cost of the structure and supporting piping systems is estimated to be 4.1 million dollars. Total dose savings per year could be as high as 70 man Rem for resin processing alone. The ability to store refueling equipment, process contaminated oils, load and unload trucks and containers regardless of weather conditions and support repair work on equipment greatly enhances the cost effectiveness of the project. It will take at least one year of operation of the facility to accurately assess the true cost savings to Alabama Power Company. The morale factor for the Waste and Decon Group has escalated measurably due to the dose reduction to our personnel. Plant and company management are well pleased due to the possibility of a spill or release to the environment has been eliminated which was on intangible cost. Facility construction has been completed as of this date and resin transfer anticipated within the next few days. Some of the problems encountered in planning and constructing this solidification and dewatering facility are presented. A safety evaluation for the facility is included in the appendix

  15. Power Systems Development Facility Gasification Test Campaign TC24

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2008-03-30

    In support of technology development to utilize coal for efficient, affordable, and environmentally clean power generation, the Power Systems Development Facility (PSDF), located in Wilsonville, Alabama, routinely demonstrates gasification technologies using various types of coals. The PSDF is an engineering scale demonstration of key features of advanced coal-fired power systems, including a KBR Transport Gasifier, a hot gas particulate control device, advanced syngas cleanup systems, and high-pressure solids handling systems. This report summarizes the results of TC24, the first test campaign using a bituminous coal as the feedstock in the modified Transport Gasifier configuration. TC24 was conducted from February 16, 2008, through March 19, 2008. The PSDF gasification process operated for about 230 hours in air-blown gasification mode with about 225 tons of Utah bituminous coal feed. Operational challenges in gasifier operation were related to particle agglomeration, a large percentage of oversize coal particles, low overall gasifier solids collection efficiency, and refractory degradation in the gasifier solids collection unit. The carbon conversion and syngas heating values varied widely, with low values obtained during periods of low gasifier operating temperature. Despite the operating difficulties, several periods of steady state operation were achieved, which provided useful data for future testing. TC24 operation afforded the opportunity for testing of various types of technologies, including dry coal feeding with a developmental feeder, the Pressure Decoupled Advanced Coal (PDAC) feeder; evaluating a new hot gas filter element media configuration; and enhancing syngas cleanup with water-gas shift catalysts. During TC24, the PSDF site was also made available for testing of the National Energy Technology Laboratory's fuel cell module and Media Process Technology's hydrogen selective membrane.

  16. What Just Happened to Me?

    Science.gov (United States)

    Peters, Dane L.

    2012-01-01

    The highly publicized story of unfathomable abuse by Penn State football coach Jerry Sandusky, as well the unfathomable response of those with the power to stop it, makes it clear that abuse can happen anywhere--and that adults need to be vigilant and educated. All of those who oversee schools must also ensure that their faculty and staff are well…

  17. Structural health monitoring and lifecycle-management for civil engineering constructions in power plants and industrial facilities; Zustandsueberwachung und Lebensdauermanagement von baulichen Einrichtungen in Kraftwerken und Industrieanlagen

    Energy Technology Data Exchange (ETDEWEB)

    Lehnen, Dieter; Demmer, Martin; Pfister, Tobias [ZERNA Planen und Pruefen GmbH, Bochum (Germany)

    2013-09-01

    In contrast to other fields of engineering, structural health monitoring and lifecycle management for civil engineering constructions in power plants and industrial facilities have to be developed yet. The necessity of this development immediately arises from the building regulations law with its extensive set of regulations as well as from economic constraints. Approaches and methods of structural health monitoring and lifecycle management for civil engineering constructions in power plants and industrial facilities could be improved intensively during recent years. The paper focuses on practical examples that show the necessity of comprehensive and strategic structural health monitoring in conjunction with lifecycle management for civil engineering constructions in power plants and industrial facilities unambiguously und clear. (orig.)

  18. Intellectual decision-making system in the context of potentially dangerous nuclear power facilities

    Directory of Open Access Journals (Sweden)

    Danilov Alexander

    2018-01-01

    Full Text Available The article deals with intelligent operation decision support system under condition of potentially hazardous nuclear facilities. The proposed system is referred to the class of advising systems and does not make final decisions in case of deviations of parameters to be analyzed, but generates general ways to solve an encountered problem and issues a set of recommendations for the plant personnel. In the article a fuzzy logic tool is used as mathematic tool. Lessons learnt from operation of nuclear facilities demonstrate that existing critical components (parts, areas, welding joints are subject to increased failure under conditions of high operational loads, including beyond design loads and negative environmental impact. Usually in that situation there is probability of equipment integrity failure, when the unit is at power, with severe defect downing. For instance, the coolant leak and potential development of initial penetration defect to critical dimensions. In other words, in fact, the final observable result is always one – formation and development of operational crack which jeopardizes design integrity of the component and, accordingly, seriously compromises the nuclear power unit operation. The proposed situational model is linked with real knowledge data base where generated situational pairs are stored. The expert system is used for knowledge data base formation. Actually the proposed system consists of two independent fuzzy systems. From mathematical tool point of view, the advantage of such systems combination is lack of defuzzification unit in the first system and fuzzification unit in the second one.

  19. Aseismatic design and safety of nuclear power generation facilities. Research in Central Research Institute of Electric Power Industry

    International Nuclear Information System (INIS)

    1995-01-01

    In order to contribute to the aseismatic design of nuclear power generation facilities, this Research Institute has carried out the observation on the site of buildings in Matsushiro earthquake, the experiment on a large vibration table, the vibration experiment on actual buildings and so on, thus made clear the method of evaluating the dynamic model of buildings and foundation grounds. Also it cooperated in the determination of input earthquake motion which is important for aseismatic design by carrying out the evaluation of the activity of faults the observation of strong earthquakes, and the elucidation and evaluation of the characteristics of earthquake motion. It has made the standard for evaluating the fault activity and the stability in earthquakes of the foundation and surrounding grounds of power stations. The development of new underground location technology, the location on Quaternary grounds and the location on the sea, and the research on developing the aseismatic construction of FBRs are in progress. The survey and evaluation of fault activities, the evaluation of earthquake input, the limit state design of important outdoor structures, the new location technology for nuclear power stations, and the development of the buckling and base isolation design of FBRs are reported. (K.I.)

  20. Magnetohydrodynamics (MHD) Engineering Test Facility (ETF) 200 MWe power plant. Conceptual Design Engineering Report (CDER). Volume 2: Engineering. Volume 3: Costs and schedules. Final Report

    International Nuclear Information System (INIS)

    1981-09-01

    Engineering design details for the principal systems, system operating modes, site facilities, and structures of an engineering test facility (ETF) of a 200 MWE power plant are presented. The ETF resembles a coal-fired steam power plant in many ways. It is analogous to a conventional plant which has had the coal combustor replaced with the MHD power train. Most of the ETF components are conventional. They can, however, be sized or configured differently or perform additional functions from those in a conventional coal power plant. The boiler not only generates steam, but also performs the functions of heating the MHD oxidant, recovering seed, and controlling emissions

  1. Low power microwave tests on RF gun prototype of the Iranian Light Source Facility

    Directory of Open Access Journals (Sweden)

    A Sadeghipanah

    2017-08-01

    Full Text Available In this paper, we introduce RF electron gun of Iranian Light Source Facility (ILSF pre-injection system. Design, fabrication and low-power microwave tests results of the prototype RF electron gun have been described in detail. This paper also explains the tuning procedure of the prototype RF electron gun to the desired resonant frequency. The outcomes of this project brighten the path to the fabrication of the RF electron gun by the local industries  

  2. Water intaking facility of nuclear power plant

    International Nuclear Information System (INIS)

    Koyama, Kazuhito; Iwata, Nobukatsu; Ochiai, Kanehiro.

    1994-01-01

    In a water intaking facility of a nuclear power plant, a dam is disposed at a position near a sea shore for preventing sea water introduced in open conduit from flowing to the outer sea upon ebbing of tsunamis. The upper end of the dam is set lower than the lower end of a water-intake pipe of a sea water pump of an ordinary system. A water-intake pipe is disposed to such a length that a sea water pump of an emergency system continues to suck the sea water when the water level of the introduced sea water is lowered than the upper end of the dam during the ebb tide. In addition, a means for stopping the operation of the sea water pump of the ordinary system upon starting of the ebb is disposed. Upon reactor scram for occurrence of earthquakes and the like, either the sea water pump in the ordinary system or the seawater pump in the emergency system operates to ensure required amount of sea water for cooling the reactor. In addition, even if the level of the sea water is lowered than the upper end of the dam, since the sea water pump in the emergency system continues to suck sea water, unnecessary suction for sea water by the ordinary sea water pumps can be eliminated. (N.H.)

  3. Fall diets of red-breasted merganser (Mergus serrator) and walleye (Sander vitreus) in Sandusky Bay and adjacent waters of western Lake Erie

    Science.gov (United States)

    Bur, M.T.; Stapanian, M.A.; Bernhardt, G.; Turner, M.W.

    2008-01-01

    Although published studies indicate the contrary, there is concern among many sport anglers that migrating red-breasted mergansers (Mergus serrator) and other waterbirds pose a competitive threat to sport fish species such as walleye (Sander vitreus) in Lake Erie. We quantified the diet of autumn-migrant mergansers and walleye during 1998-2000 in Sandusky Bay and adjacent waters of western Lake Erie. We hypothesized that the diets of both predators would be similar in species composition, but because of different foraging ecologies their diets would differ markedly in size of prey consumed. In addition to predator samples, we used trawl data from the same general area as an index of prey availability. We found that mergansers fed almost exclusively on fish (nine species). Gizzard shad (Dorosoma cepedianum), emerald shiner (Notropis atherinoides) and round goby (Neogobius melanostomus) were consumed in the greatest numbers, most frequently and comprised the greatest biomass. Walleye fed exclusively on fish: gizzard shad, alewife (Alosa psuedoharengus) and emerald shiner were consumed in the greatest numbers, most frequently and comprised the greatest biomass. Diet overlap between mergansers and walleye was 67% by weight and 66% by species frequency. Mean total lengths of gizzard shad, emerald shiner and round goby found in walleye stomachs exceeded those captured in trawls by 47%, on average. Mean total lengths of gizzard shad, emerald shiner and round goby were greater in walleye stomachs than in merganser stomachs. Mean total lengths of emerald shiner and round goby were less in merganser stomachs than in trawls. Our results suggest that although the diets of walleye and mergansers overlapped considerably, mergansers generally consumed smaller fish than walleye. Given the abundance and diversity of prey species available, and the transient nature of mergansers on Lake Erie during migration, we conclude that competition for food between these species is minimal.

  4. Experiences in the development of an emergency response facility (ERF) system for a nuclear power plant

    International Nuclear Information System (INIS)

    Seisdedos, A.; Sanchez-Fornie, M.A.

    1985-01-01

    The TMI-2 accident gave rise to a series of new requirements with which Nuclear Power Plants must comply and amongst which the implementation of emergency response facilities, particularly the SPDS, has received special attention. This paper covers the experience and problems encountered in the developing of the engineering necessary for the detailed definition of the ERF in a Nuclear Power Plant in the commercial operation phase. Also, a real example is provided for the case of a plant in the last phase of construction and installation. This will serve to illustrate each of the topics covered. (author)

  5. Decree of the Czech Labor Safety Office No. 263/1991 amending the Decree No. 76/1989 on ensuring safety of technical facilities in the nuclear power sector

    International Nuclear Information System (INIS)

    1995-01-01

    Some provisions of the Decree of the Czech Labor Safety Office No. 76/1989 on ensuring safety of technical facilities in the nuclear power sector are amended, particularly in the field of construction activities, assembling, reconstruction and repair of nuclear power facilities. The Decree entered into force on 28 June 1991. (J.B.)

  6. The industrial facility for Grouping, Storage and Disposal

    International Nuclear Information System (INIS)

    Torres, Patrice

    2013-07-01

    The industrial facility for grouping, storage and disposal (called Cires in French), in the Aube district, is run by Andra. The facility is licensed to dispose of very-low-level waste, to collect non-nuclear-power radioactive waste and to provide storage for some of the waste for which a final management solution has not yet been found. The Cires facility is located a few kilometers from the Aube disposal facility (CSA), another of Andra's waste disposal facilities, currently dealing with low- and intermediate-level, short-lived waste. Contents: Andra in the Aube district, an exemplary industrial operator - The industrial facility for grouping, storage and disposal (Cires); Disposal of very-low-level waste (VLLW); The journey taken by VLL waste; Grouping of non-nuclear-power waste; Storage of non-nuclear-power waste; The journey taken by non-nuclear-power waste; Protecting present and future generations

  7. 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.)

  8. Ice storage facilities are worthwhile for the operation of power plants. Load management with jet pumps; Eisspeicher zahlen sich fuer Kraftwerksbetrieb aus. Lastmanagement mit Strahlpumpen

    Energy Technology Data Exchange (ETDEWEB)

    Gerhold, Richard

    2012-12-15

    The significantly better alternative to hot water tanks in thermal power plants are ice storage tanks and steam jet refrigeration plants. These facilities form ice, supply district heating and produce heat from the environment. Furthermore, these facilities produce additional peak load electricity nearly daily, so that several large power plants become dispensable. How this is possible in a simple and low-cost manner, is described in the contribution under consideration.

  9. Nuclear power-related facilities and neighboring land price: a case study on the Mutsu-Ogawara region, Japan.

    Science.gov (United States)

    Yamane, Fumihiro; Ohgaki, Hideaki; Asano, Kota

    2011-12-01

    From the perspective of risk, nuclear-power-related facilities (NPRFs) are often regarded as locally undesirable land use. However, construction of NPRFs contributes to social infrastructural improvement and job creation in the host communities. This raises a question: How large are these positive and negative effects? To approach this question from an economic viewpoint, we estimated the hedonic land price function for the Mutsu-Ogawara region of Japan from 1976 to 2004 and analyzed year-by-year fluctuations in land prices around the NPRFs located there. Land prices increased gradually in the neighborhood of the nuclear fuel cycle facilities (NFCFs) in Rokkasho Village, except for some falling (i) from 1982 to 1983 (the first official announcement of the project of construction came in 1983), (ii) from 1987 to 1988 (in 1988, the construction began and opposition movements against the project reached their peak), and (iii) from 1998 to 1999 (the pilot carry-in of spent fuels into the reprocessing plant began in 1998). Land prices around the Higashidori Nuclear Power Plant decreased during the period 1981-1982, when the Tohoku Electric Power Corp. and Tokyo Electric Power Corp. announced their joint construction plan. On the other hand, we obtained some results, even though not significant, indicating that land prices around Ohminato and Sekinehama harbors changed with the arrival and departure of the nuclear ship Mutsu, which suffered a radiation leak in 1974. © 2011 Society for Risk Analysis.

  10. Study on the RF power necessary to ignite plasma for the ICP test facility at HUST

    Energy Technology Data Exchange (ETDEWEB)

    Yue, Haikun [School of Electronic Information and Communications, Huazhong University of Science and Technology, Wuhan (China); State Key Laboratory of Advanced Electromagnetic Engineering and Technology, Huazhong University of Science and Technology, Wuhan (China); Li, Dong; Wang, Chenre; Li, Xiaofei; Chen, Dezhi; Liu, Kaifeng; Zhou, Chi; Pan, Ruimin [State Key Laboratory of Advanced Electromagnetic Engineering and Technology, Huazhong University of Science and Technology, Wuhan (China)

    2015-10-15

    An Radio-Frequency (RF) Inductively Coupled Plasma (ICP) ion source test facility has been successfully developed at Huazhong University of Science and Technology (HUST). As part of a study on hydrogen plasma, the influence of three main operation parameters on the RF power necessary to ignite plasma was investigated. At 6 Pa, the RF power necessary to ignite plasma influenced little by the filament heating current from 5 A to 9 A. The RF power necessary to ignite plasma increased rapidly with the operation pressure decreasing from 8 Pa to 4 Pa. The RF power necessary to ignite plasma decreased with the number of coil turns from 6 to 10. During the experiments, plasma was produced with the electron density of the order of 10{sup 16}m{sup -3} and the electron temperature of around 4 eV. (copyright 2015 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

  11. Power supply design for Hadron Facility

    International Nuclear Information System (INIS)

    Karady, G.; Kansog, J.; Thiessen, H.A.; Schneider, E.

    1987-01-01

    Recently, a study investigated the feasibility of building a large 60 GeV, kaon factory accelerator. This paper presents the conceptual design of the magnet power supplies and energy storage system. In this study the following three systems were investigated: (a) power supply using storage generator; (b) power supply using inductive storage device; and (c) resonant power supplies. These systems were analyzed from both technical and economical points of view. It was found that all three systems are feasible and can be built using commercially available components. From a technical point of view, the system using inductive storage is the most advantageous. The resonant power supply is the most economical solution

  12. Preliminary reactor physics calculations for Exxon LWR fuel testing in the power burst facility

    International Nuclear Information System (INIS)

    Olson, W.O.; Nigg, D.W.

    1981-05-01

    The PFB reactor is being considered as an irradiation facility to test LWR fuel rods for Exxon Nuclear Company. Requested test conditions are 18 kW/ft axial peak steady state power in 2.5% initial enrichment, 20,000 MWd/Tu exposed rods. Multigroup transport theory calculations (S/sub n/ and Monte Carlo) showed that this was unattainable in the standard PBF test loop. Thus, a flux multiplier was developed in the form of a Zr-2-clad 0.15-inch thick cylindrical shell of 35% enriched, 88% T.D. UO 2 replacing the flow divider, surrounding the rod within the in-pile tube in PFB. With this flux multiplier installed and assuming an average water density of 0.86 g/cm 3 within the test loop, a Figure of Merit (FOM) for a single-rod test assembly of 0.86 kW/ft-MW +- 5% (at 95% confidence level) was calculated. This FOM is the axial peak linear test rod power per megawatt of reactor power. A reactor power of about 21 megawatts will therefore be required to supply the requested linear test rod axial peak heating rate of 18 kW/ft

  13. Aseismatic design and safety of nuclear power generation facilities. On aseismatic capability of commercial nuclear power stations

    International Nuclear Information System (INIS)

    Kato, Muneaki

    1995-01-01

    In view of the great Hanshin earthquake, the aseismatic safety of the important facilities in nuclear power stations is ensured by the location direct on base rocks, the design with the earthquake force at least three times as large as that in the building standard, and the consideration of the earthquakes due to active faults as design earthquake. The basic policy of the aseismatic design of nuclear power stations is described. The determination of the earthquake motions due to strongest earthquake and utmost limit earthquake for design, the survey of the geological features and ground of the sites and so on are explained. In the aseismatic design of buildings and structures, structural planning, the modeling for the aseismatic analysis of buildings, the analysis of time historical response and so on are carried out. In the aseismatic design of equipment and piping systems, the planning of aseismatic support structures, the aseismatic design and the analysis of time historical response, the spectral modal analysis for other systems such as multiple material point system and so on are described. The tests and researches related to the aseismatic design are reported. (K.I.)

  14. Magnetohydrodynamics (MHD) Engineering Test Facility (ETF) 200 MWe power plant. Design Requirements Document (DRD)

    Science.gov (United States)

    Rigo, H. S.; Bercaw, R. W.; Burkhart, J. A.; Mroz, T. S.; Bents, D. J.; Hatch, A. M.

    1981-01-01

    A description and the design requirements for the 200 MWe (nominal) net output MHD Engineering Test Facility (ETF) Conceptual Design, are presented. Performance requirements for the plant are identified and process conditions are indicated at interface stations between the major systems comprising the plant. Also included are the description, functions, interfaces and requirements for each of these major systems. The lastest information (1980-1981) from the MHD technology program are integrated with elements of a conventional steam electric power generating plant.

  15. 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)

  16. LWR fuel rod testing facilities in high flux reactor (HFT) Petten for investigation of power cycling and ramping behaviour

    Energy Technology Data Exchange (ETDEWEB)

    Markgraf, J; Perry, D; Oudaert, J [Commission of the European Communities, Joint Reserach Centre, Petten Establishment, Petten (Netherlands)

    1983-06-01

    LWR fuel rod irradiation experiments are being performed in HFR's Pool Side Facility (PSF) by means of pressurized boiling water capsules (BWFC). For more than 6 years the major application of these devices has been in performing irradiation programs to investigate the power ramp behaviour of PWR and BWR rods which have been pre-irradiated in power reactors. Irradiation devices with various types of monitoring instrumentation are available, e.g. for fuel rod length, fuel stack length, fuel rod internal pressure and fuel rod central temperature measurements. The application scope covers PWR and BWR fuel rods, with burn-up levels up to 45 MWd/kg(U), max. linear heat generation rates up to 700 W/cm and simulation of constant power change rates between 0.05 and 1000 W/cm.min. The paper describes the different designs of LWR fuel rod testing facilities and associated non-destructive testing devices in use at the HFR Petten. It also addresses the new test capabilities that will become available after exchange of the HFR vessel in 1983. Furthermore it shows some typical results. (author)

  17. Qualification and actuation of the independent technical supervision organisms in nuclear power plants and others facilities

    International Nuclear Information System (INIS)

    1999-09-01

    This norm presents the following objectives: establishment of the Brazilian National Nuclear Energy Commission requirements for qualifying an institution as independent technical supervision organization, in a specific area of activity related to nuclear power plants and others nuclear or radioactive facilities as appropriated; regulation of the independent technical supervision and others complementary activities to be executed by an independent technical supervision organism

  18. Application of low bitrate image coding to surveillance of electric power facilities. Part 1. Proposal of low bitrate coding for surveillance of electric power facilities and examination of facilities region extraction method; Denryoku setsubi kanshi eno tei rate fugoka hoshiki no tekiyo. 1. Setsubi kanshiyo fugoka hoshiki no teian to setsubi ryoiki chushutsuho no kento

    Energy Technology Data Exchange (ETDEWEB)

    Murata, H.; Ishino, R. [Central Research Institute of Electric Power Industry, Tokyo (Japan)

    1996-03-01

    Current status of low bitrate image coding has been investigated, and a low bitrate coding suitable for the surveillance of electric power facilities has been proposed, to extract its problems to be solved. For the conventional image coding, the waveform coding has been used by which the images are processed as signals. While, for the MPEG-4, a coding method with considering the image information has been proposed. For these coding methods, however, image information lacks details primarily, when lowering the bitrate. Accordingly, these methods can not be applied when the details in the images are important, such as in the case of surveillance of facilities. Then, the coding method has been proposed by expanding the partially detailed coding, and by separating constituent images of facilities, such as power cables and steel towers, designated by operators. It is the special feature of this method that the method can easily respond to the low bitrate and the detailed information can be conserved by using the structure extraction coding for the designated partial image which is generally processed by the low bitrate waveform coding. 29 refs., 17 figs., 1 tab.

  19. Power Systems Development Facility Gasification Test Run TC07

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2002-04-05

    This report discusses Test Campaign TC07 of the Kellogg Brown & Root, Inc. (KBR) Transport Reactor train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Reactor is an advanced circulating fluidized-bed reactor designed to operate as either a combustor or a gasifier using a particulate control device (PCD). The Transport Reactor was operated as a pressurized gasifier during TC07. Prior to TC07, the Transport Reactor was modified to allow operations as an oxygen-blown gasifier. Test Run TC07 was started on December 11, 2001, and the sand circulation tests (TC07A) were completed on December 14, 2001. The coal-feed tests (TC07B-D) were started on January 17, 2002 and completed on April 5, 2002. Due to operational difficulties with the reactor, the unit was taken offline several times. The reactor temperature was varied between 1,700 and 1,780 F at pressures from 200 to 240 psig. In TC07, 679 hours of solid circulation and 442 hours of coal feed, 398 hours with PRB coal and 44 hours with coal from the Calumet mine, and 33 hours of coke breeze feed were attained. Reactor operations were problematic due to instrumentation problems in the LMZ resulting in much higher than desired operating temperatures in the reactor. Both reactor and PCD operations were stable and the modifications to the lower part of the gasifier performed well while testing the gasifier with PRB coal feed.

  20. Administrative procedures linked with power production facilities that use renewable energy sources. Report made in application of article 6 of directive 2001/77/CE from October 27, 2001

    International Nuclear Information System (INIS)

    2001-10-01

    This report presents an evaluation of the legislative and regulatory framework relative to power generation facilities that use renewable energy sources. It presents also the actions that have been carried out to reduce the obstacles to the development of these facilities (access to the power distribution and transportation grid). (J.S.)

  1. 18 CFR 1317.410 - Comparable facilities.

    Science.gov (United States)

    2010-04-01

    ... 18 Conservation of Power and Water Resources 2 2010-04-01 2010-04-01 false Comparable facilities... facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but such facilities provided for students of one sex shall be comparable to such facilities provided...

  2. The Cost-Optimal Distribution of Wind and Solar Generation Facilities in a Simplified Highly Renewable European Power System

    Science.gov (United States)

    Kies, Alexander; von Bremen, Lüder; Schyska, Bruno; Chattopadhyay, Kabitri; Lorenz, Elke; Heinemann, Detlev

    2016-04-01

    The transition of the European power system from fossil generation towards renewable sources is driven by different reasons like decarbonisation and sustainability. Renewable power sources like wind and solar have, due to their weather dependency, fluctuating feed-in profiles, which make their system integration a difficult task. To overcome this issue, several solutions have been investigated in the past like the optimal mix of wind and PV [1], the extension of the transmission grid or storages [2]. In this work, the optimal distribution of wind turbines and solar modules in Europe is investigated. For this purpose, feed-in data with an hourly temporal resolution and a spatial resolution of 7 km covering Europe for the renewable sources wind, photovoltaics and hydro was used. Together with historical load data and a transmission model , a simplified pan-European power power system was simulated. Under cost assumptions of [3] the levelized cost of electricity (LCOE) for this simplified system consisting of generation, consumption, transmission and backup units is calculated. With respect to the LCOE, the optimal distribution of generation facilities in Europe is derived. It is shown, that by optimal placement of renewable generation facilities the LCOE can be reduced by more than 10% compared to a meta study scenario [4] and a self-sufficient scenario (every country produces on average as much from renewable sources as it consumes). This is mainly caused by a shift of generation facilities towards highly suitable locations, reduced backup and increased transmission need. The results of the optimization will be shown and implications for the extension of renewable shares in the European power mix will be discussed. The work is part of the RESTORE 2050 project (Wuppertal Institute, Next Energy, University of Oldenburg), that is financed by the Federal Ministry of Education and Research (BMBF, Fkz. 03SFF0439A). [1] Kies, A. et al.: Kies, Alexander, et al

  3. Operational status of nuclear facilities in Japan. 2008 edition

    International Nuclear Information System (INIS)

    2008-01-01

    This document is a summary of the outline of the safety regulation administration of nuclear facilities as well as various data on the commercial nuclear power reactor facilities, research and development nuclear power reactor facilities, fabrication facilities, reprocessing facilities, and disposal facilities in fiscal year 2007 (from April 2007 to March 2008). I sincerely hope this document is used widely by many people engaged in work related to ensuring nuclear safety. (J.P.N.)

  4. Operational status of nuclear facilities in Japan. 2010 edition

    International Nuclear Information System (INIS)

    2010-01-01

    This document is a summary of the outline of the safety regulation administration of nuclear facilities as well as various data on the commercial nuclear power reactor facilities, research and development nuclear power reactor facilities, fabrication facilities, reprocessing facilities, and disposal facilities in fiscal year 2009 (from April 2009 to March 2010). We sincerely hope this document is used widely by many people engaged in work related to ensuring nuclear safety. (author)

  5. Investigation on Transmission and Substation Facilities of Sichuan Power Grid in Wenchuan Earthquake

    Institute of Scientific and Technical Information of China (English)

    Yu Yongqing; Li Guangfan; Li Peng; Zhu Quanjun; Yuan Dalu; Wang Chengyu; Li Jinzhong; Huang Huang; Li Lixin; Zhang Xinghai; Liu Jingmin

    2009-01-01

    @@ On May 12,2008,an earthquake of Ms 8.0 hit the area around Wenchuan County,Sichuan Province,China.It has been one of the most destructive earthquakes since the founding of P.R.China in 1949.The quake caused not only tremendous loss of life and wealth,but also severe damage to transmission and substation facilities.After the disaster,an expert group from China Electric Power Research Institute (CEPRI)was sent for on-site investigation.This paper is a summary of the investigation,in which suggestions for electric equipment to resist earthquake disasters are also proponed.

  6. CONCERT A high power proton accelerator driven multi-application facility concept

    CERN Document Server

    Laclare, J L

    2000-01-01

    A new generation of High Power Proton Accelerator (HPPA) is being made available. It opens new avenues to a long series of scientific applications in fundamental and applied research, which can make use of the boosted flux of secondary particles. Presently, in Europe, several disciplines are preparing their project of dedicated facility, based on the upgraded performances of HPPAs. Given the potential synergies between these different projects, for reasons of cost effectiveness, it was considered appropriate to look into the possibility to group a certain number of these applications around a single HPPA: CONCERT project left bracket 1 right bracket . The ensuing 2-year feasibility study organized in collaboration between the European Spallation Source and the CEA just started. EURISOL left bracket 2 right bracket project and CERN participate in the steering committee.

  7. Facilities inventory protection for nuclear facilities

    International Nuclear Information System (INIS)

    Schmitt, F.J.

    1989-01-01

    The fact that shut-down applications have been filed for nuclear power plants, suggests to have a scrutinizing look at the scopes of assessment and decision available to administrations and courts for the protection of facilities inventories relative to legal and constitutional requirements. The paper outlines the legal bases which need to be observed if purposeful calculation is to be ensured. Based on the different actual conditions and legal consequences, the author distinguishes between 1) the legal situation of facilities licenced already and 2) the legal situation of facilities under planning during the licencing stage. As indicated by the contents and restrictions of the pertinent provisions of the Atomic Energy Act and by the corresponding compensatory regulation, the object of the protection of facilities inventor in the legal position of the facility owner within the purview of the Atomic Energy Act, and the licensing proper. Art. 17 of the Atomic Energy Act indicates the legislators intent that, once issued, the licence will be the pivotal point for regulations aiming at protection and intervention. (orig./HSCH) [de

  8. Proceedings of the first international seminar on seismic base isolation for nuclear power facilities

    International Nuclear Information System (INIS)

    1989-01-01

    The First International Seminar on Seismic Base Isolation of Nuclear Power Facilities was organized by the authors of this paper. It was held in San Francisco, California, USA, on August 21--22, 1989, in conjunction with the tenth International Conference on Structural Mechanics in Reactor Technology (SMiRT-10). The purpose of the seminar was to provide an international forum for discussion on the application of base isolation to nuclear power plants and of its effectiveness in reducing seismic loads and permitting standard plant designs. It also provided an opportunity for technical interchange between base isolation system designers, structural engineers, and nuclear power plant engineers. Seismic isolation is certainly one of the most significant earthquake engineering developments in recent years. This was clearly demonstrated by the very large attendance at this seminar and the various papers presented. Isolation system act as filters that reduce the seismic forces and increase the ability of isolated structures and their contents to withstand the damaging effects of earthquake motions. Each individual paper has been cataloged separately

  9. A personal computer code for seismic evaluations of nuclear power plant facilities

    International Nuclear Information System (INIS)

    Xu, J.; Graves, H.

    1990-01-01

    A wide range of computer programs and modeling approaches are often used to justify the safety of nuclear power plants. It is often difficult to assess the validity and accuracy of the results submitted by various utilities without developing comparable computer solutions. Taken this into consideration, CARES is designed as an integrated computational system which can perform rapid evaluations of structural behavior and examine capability of nuclear power plant facilities, thus CARES may be used by the NRC to determine the validity and accuracy of analysis methodologies employed for structural safety evaluations of nuclear power plants. CARES has been designed to: operate on a PC, have user friendly input/output interface, and have quick turnaround. The CARES program is structured in a modular format. Each module performs a specific type of analysis. The basic modules of the system are associated with capabilities for static, seismic and nonlinear analyses. This paper describes the various features which have been implemented into the Seismic Module of CARES version 1.0. In Section 2 a description of the Seismic Module is provided. The methodologies and computational procedures thus far implemented into the Seismic Module are described in Section 3. Finally, a complete demonstration of the computational capability of CARES in a typical soil-structure interaction analysis is given in Section 4 and conclusions are presented in Section 5. 5 refs., 4 figs

  10. High efficiency combined heat and power facilities - benefits and barriers

    International Nuclear Information System (INIS)

    Klein, M.

    2001-01-01

    There are important linkages between the economy, energy production, the environment and our health. Where thermal energy is needed, distributed Combined Heat and Power facilities, using gas turbines, reciprocating engines and future fuel cells can provide significant improvements to our long term mix of energy production. Local generation can also have benefits in security of energy supply and economic savings. This paper is intended to discuss the relevant air pollution and greenhouse gas emissions from modem CHP plants, the emission prevention and reduction methods available, and their operating experience and cost-effectiveness. Mention is made of recently constructed industrial and commercial plants, and institutional barriers to further development. Solutions described for these barriers include the need for more awareness of opportunities, improved access to the electricity grid, the proper design balance between thermal and electric for CHP systems rather than large combined cycles, improved corporate taxation incentives, and the assessment of all environmental and economic benefits when considering such cleaner sources in a restructured energy market. (author)

  11. Facility for protection of technological, especially power assemblies

    International Nuclear Information System (INIS)

    Cichon, S.; Hahn, J.; Malatek, K.; Randak, O.; Vitovec, P.; Zidek, M.

    1987-01-01

    The facility consists of sensors producing analog signals, used as input information for the evaluation of process conditions or equipment failures. The sensors are fitted to partial functional parts of technological assemblies, such as nuclear reactors. The individual sensors are connected via unification converters to the respective protection units. The facility is resistant to breakdowns of the analog sensors and other components including the computer; it features the possibility of in-service failure detection and the capability of immediate regeneration following a failure. This capability prevents, with high probability, the production of non-accident failures of the technological assembly. The block diagram is described of the facility and its operation in the event of an emergency. (J.B.). 1 fig

  12. MELCOR modeling of the PBF [Power Burst Facility] Severe Fuel Damage Test 1-4

    International Nuclear Information System (INIS)

    Madni, I.K.

    1990-01-01

    This paper describes a MELCOR Version 1.8 simulation of the Power Burst Facility (PBF) Severe Fuel Damage (SFD) Test 1--4. The input data for the analysis were obtained from the Test Results Report and from SCDAP/RELAP5 input. Results are presented for the transient liquid level in the test bundle, clad temperatures, shroud temperatures, clad oxidation and hydrogen generation, bundle geometry changes, fission product release, and heat transfer to the bypass flow. Comparisons are made with experimental data and with SCDAP/RELAP5 calculations. 10 refs., 7 figs

  13. Safety at basic nuclear facilities other than nuclear power plants. Lessons learned from significant events reported in 2011 and 2012

    International Nuclear Information System (INIS)

    2014-01-01

    The third report on the safety of basic nuclear installations in France other than power reactors presents an IRSN's analysis of significant events reported to the Nuclear Safety Authority in the years 2011 and 2012. It covers plants, laboratories, research reactors and facilities for the treatment, storage or disposal of waste. This report aims to contribute to a better understanding by stakeholders and more widely by the public of the safety and radiation protection issues associated with the operation of nuclear facilities, the progress made in terms of safety as well as the identified deficiencies. The main trend shows, once again, the significant role of organizational and human factors in the significant events that occurred in 2011 and 2012, of which the vast majority are without noteworthy consequences. Aging mechanisms are another major cause of equipment failure and require special attention. The report also provides IRSN's analysis of specific events that are particularly instructive for facility safety and a synthesis of assessments performed by IRSN on topics that are important for safety and radiation protection. IRSN also includes an overview of its analysis of measures proposed by licensees for increasing the safety of their facilities after the March 2011 accident at the Fukushima Daiichi nuclear power plant in Japan, which consist of providing a 'hardened safety core' to confront extreme situations (earthquake, flooding, etc.) that are unlikely but plausible and can bring about levels of hazards higher than those taken into account in the design of the facilities

  14. CALCULATION OF OPERATING PARAMETERS OF HIGH-VOLTAGE POWER TAKE-OFF SYSTEM FOR THE PHOTOVOLTAIC FACILITY

    Directory of Open Access Journals (Sweden)

    R.V. Zaitsev

    2016-09-01

    Full Text Available Purpose. To ensure maximum production of electric power by photovoltaic vacilities, in addition to using highly efficient photovoltaic modules equipped with solar radiation concentrators must use a highly effective power take-off system. This paper is inscribed to solving the problem of a highly efficient and economic power take-off system development. Methodology. To solving the problem, we implemented three stages. On the first stage examines the dependence of electrical power from the intensity of the incident solar radiation. Based on this, the second stage is calculated the DC-DC converter resonant circuit and its working parameters, and developed circuit diagram of DC-DC converter. On the third stage, we carry out an analysis of power take-off system with step up DC-DC converter working. Results. In this paper, we carry out the analysis of working efficiency for photovoltaic facility power take-off system with step-up boost converter. The result of such analysis show that the efficiency of such system in a wide range of photovoltaic energy module illumination power is at 0.92, whereas the efficiency of classic power take-off systems does not exceed 0.70. Achieved results allow designing a circuit scheme of a controlled bridge resonant step-up converter with digital control. Proposed scheme will ensure reliable operation, fast and accurate location point of maximum power and conversion efficiency up to 0.96. Originality. Novelty of proposed power take-off system solution constitute in implementation of circuit with DC-DC converters, which as it shown by results of carrying out modeling is the most effective. Practical value. Practical implementation of proposed power take-off system design will allow reducing losses in connective wires and increasing the efficiency of such a system up to 92.5% in wide range of photovoltaic energy modules illumination.

  15. The Idaho Power Burst Facility/Boron Neutron Capture Therapy (PBF/BNCT) Program overview

    International Nuclear Information System (INIS)

    Dorn, R.V. III; Griebenow, M.L.; Ackermann, A.L.; Miller, L.G.; Miller, D.L.; Wheeler, F.J.; Bradshaw, K.M.; Wessol, D.E.; Harker, Y.D.; Nigg, D.W.; Randolph, P.D.; Bauer, W.F.; Gavin, P.R.; Richards, T.L.

    1992-01-01

    The Power Burst Facility/Boron Neutron Capture Therapy (PBF/BNCT) Program has been funded since 1988 to evaluate brain tumor treatment using Na 2 B 12 H 11 SH (borocaptate sodium or BSH) and epithermal neutrons. The PBF/BNCT Program pursues this goal as a comprehensive, multidisciplinary, multiorganizational endeavor applying modern program management techniques. The initial focus was to: (1) establish a representative large animal model and (2) develop the generic analytical and measurement capabilities require to control treatment repeatability and determine critical treatment parameters independent of tumor type and body location. This paper will identify the PBF/BNCT Program elements and summarize the status of some of the developed capabilities

  16. A personal computer code for seismic evaluations of nuclear power plant facilities

    International Nuclear Information System (INIS)

    Xu, J.; Graves, H.

    1991-01-01

    In the process of review and evaluation of licensing issues related to nuclear power plants, it is essential to understand the behavior of seismic loading, foundation and structural properties and their impact on the overall structural response. In most cases, such knowledge could be obtained by using simplified engineering models which, when properly implemented, can capture the essential parameters describing the physics of the problem. Such models do not require execution on large computer systems and could be implemented through a personal computer (PC) based capability. Recognizing the need for a PC software package that can perform structural response computations required for typical licensing reviews, the US Nuclear Regulatory Commission sponsored the development of a PC operated computer software package CARES (Computer Analysis for Rapid Evaluation of Structures) system. This development was undertaken by Brookhaven National Laboratory (BNL) during FY's 1988 and 1989. A wide range of computer programs and modeling approaches are often used to justify the safety of nuclear power plants. It is often difficult to assess the validity and accuracy of the results submitted by various utilities without developing comparable computer solutions. Taken this into consideration, CARES is designed as an integrated computational system which can perform rapid evaluations of structural behavior and examine capability of nuclear power plant facilities, thus CARES may be used by the NRC to determine the validity and accuracy of analysis methodologies employed for structural safety evaluations of nuclear power plants. CARES has been designed to operate on a PC, have user friendly input/output interface, and have quick turnaround. This paper describes the various features which have been implemented into the seismic module of CARES version 1.0

  17. Operational results for the raster scanning power supply system constructed at the Bevalac Biomedical Facility

    International Nuclear Information System (INIS)

    Stover, G.; Halliwell, J.; Nyman, M.; Dwinell, R.

    1989-03-01

    A raster scanning power supply for controlling an 8.0 Tesla-meter relativistic heavy-ion beam at the Biomedical Facility has been recently completed and is undergoing electrical testing before on- line operation in 1989. The scanner system will provide tightly controlled beam uniformity and off-axis treatment profiles with large aspect ratios and unusual dimensions. This article will discuss original specifications, agreement with measured results and special device performance (i.e. GTOs, FET actuator assembly, etc.). 5 refs., 4 figs

  18. Nuclear safety and radiation protection report of the basic nuclear facilities of the Tricastin nuclear power plant - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Tricastin nuclear power plant (INB 87 and 88, Saint-Paul-Trois-Chateaux, Drome (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  19. 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

  20. LLNL superconducting magnets test facility

    Energy Technology Data Exchange (ETDEWEB)

    Manahan, R; Martovetsky, N; Moller, J; Zbasnik, J

    1999-09-16

    The FENIX facility at Lawrence Livermore National Laboratory was upgraded and refurbished in 1996-1998 for testing CICC superconducting magnets. The FENIX facility was used for superconducting high current, short sample tests for fusion programs in the late 1980s--early 1990s. The new facility includes a 4-m diameter vacuum vessel, two refrigerators, a 40 kA, 42 V computer controlled power supply, a new switchyard with a dump resistor, a new helium distribution valve box, several sets of power leads, data acquisition system and other auxiliary systems, which provide a lot of flexibility in testing of a wide variety of superconducting magnets in a wide range of parameters. The detailed parameters and capabilities of this test facility and its systems are described in the paper.

  1. Research and design of scanning power supply for deep tumor therapy facility with heavy ions accelerator in Lanzhou

    International Nuclear Information System (INIS)

    Huang Yuzhen; Liu Yuntao; Chen Youxin; Gao Daqing; Zhang Shu; Gao Yalin

    2009-01-01

    This paper describes the technique targets and operation principle of the scanning power supply for the deep tumor therapy facility with heavy ions in Cooler-Storage-Ring of the Heavy Ion Research Facility in Lanzhou (HIRFL-CSR). To ensure the specified accuracy of the current, the hysteresis loop control strategy was adopted, and tracking error was constrained in the specified tolerance. One prototype was designed and installed. And the simulation results and test results were listed in the paper. The results show that all the targets can meet the design requirements, and that the circuit configuration and hysteresis loop control strategy selected are practicable. (authors)

  2. The National Carbon Capture Center at the Power Systems Development Facility: Topical Report

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2011-03-01

    The Power Systems Development Facility (PSDF) is a state-of-the-art test center sponsored by the U.S. Department of Energy and dedicated to the advancement of clean coal technology. In addition to the development of advanced coal gasification processes, the PSDF features the National Carbon Capture Center (NCCC) to study CO2 capture from coal-derived syngas and flue gas. The newly established NCCC will include multiple, adaptable test skids that will allow technology development of CO2 capture concepts using coal-derived syngas and flue gas in industrial settings. Because of the ability to operate under a wide range of flow rates and process conditions, research at the NCCC can effectively evaluate technologies at various levels of maturity. During the Budget Period One reporting period, efforts at the PSDF/NCCC focused on developing a screening process for testing consideration of new technologies; designing and constructing pre- and post-combustion CO2 capture facilities; developing sampling and analytical methods; expanding fuel flexibility of the Transport Gasification process; and operating the gasification process for technology research and for syngas generation to test syngas conditioning technologies.

  3. Microscale air quality impacts of distributed power generation facilities.

    Science.gov (United States)

    Olaguer, Eduardo P; Knipping, Eladio; Shaw, Stephanie; Ravindran, Satish

    2016-08-01

    The electric system is experiencing rapid growth in the adoption of a mix of distributed renewable and fossil fuel sources, along with increasing amounts of off-grid generation. New operational regimes may have unforeseen consequences for air quality. A three-dimensional microscale chemical transport model (CTM) driven by an urban wind model was used to assess gaseous air pollutant and particulate matter (PM) impacts within ~10 km of fossil-fueled distributed power generation (DG) facilities during the early afternoon of a typical summer day in Houston, TX. Three types of DG scenarios were considered in the presence of motor vehicle emissions and a realistic urban canopy: (1) a 25-MW natural gas turbine operating at steady state in either simple cycle or combined heating and power (CHP) mode; (2) a 25-MW simple cycle gas turbine undergoing a cold startup with either moderate or enhanced formaldehyde emissions; and (3) a data center generating 10 MW of emergency power with either diesel or natural gas-fired backup generators (BUGs) without pollution controls. Simulations of criteria pollutants (NO2, CO, O3, PM) and the toxic pollutant, formaldehyde (HCHO), were conducted assuming a 2-hr operational time period. In all cases, NOx titration dominated ozone production near the source. The turbine scenarios did not result in ambient concentration enhancements significantly exceeding 1 ppbv for gaseous pollutants or over 1 µg/m(3) for PM after 2 hr of emission, assuming realistic plume rise. In the case of the datacenter with diesel BUGs, ambient NO2 concentrations were enhanced by 10-50 ppbv within 2 km downwind of the source, while maximum PM impacts in the immediate vicinity of the datacenter were less than 5 µg/m(3). Plausible scenarios of distributed fossil generation consistent with the electricity grid's transformation to a more flexible and modernized system suggest that a substantial amount of deployment would be required to significantly affect air quality on

  4. Environmental safety aspects of the new solid radioactive waste management and storage facility at the Ignalina Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Ragaisis, Valdas; Poskas, Povilas; Simonis, Vytautas; Adomaitis, Jonas Erdvilas [Lithuanian Energy Institute, Kaunas (Lithuania). Nuclear Engineering Lab.

    2011-11-15

    New solid radioactive waste management and interim storage facilities will be constructed for the Ignalina Nuclear Power Plant to support ongoing decommissioning activities, including removal and treatment of operational waste from the existing storage buildings. The paper presents approach and methods that have been used to assess radiological impacts to the general public potentially arising under normal operation and accident conditions and to demonstrate compliance with regulations in force. The assessment of impacts from normal operation includes evaluation of exposure arising from release of airborne radioactive material and from facilities and packages containing radioactive material. In addition, radiological impacts from other nearby operating and planned nuclear facilities are taken into consideration. The assessment of impacts under accident conditions includes evaluation of exposure arising from the selected design and beyond design basis accidents. (orig.)

  5. Power Systems Development Facility Gasification Test Run TC08

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2002-06-30

    This report discusses Test Campaign TC08 of the Kellogg Brown & Root, Inc. (KBR) Transport Gasifier train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Gasifier is an advanced circulating fluidized-bed gasifier designed to operate as either a combustor or a gasifier in air- or oxygen-blown mode using a particulate control device (PCD). The Transport Gasifier was operated as a pressurized gasifier in air- and oxygen-blown modes during TC08. Test Run TC08 was started on June 9, 2002 and completed on June 29. Both gasifier and PCD operations were stable during the test run with a stable baseline pressure drop. The oxygen feed supply system worked well and the transition from air to oxygen blown was smooth. The gasifier temperature was varied between 1,710 and 1,770 F at pressures from 125 to 240 psig. The gasifier operates at lower pressure during oxygen-blown mode due to the supply pressure of the oxygen system. In TC08, 476 hours of solid circulation and 364 hours of coal feed were attained with 153 hours of pure oxygen feed. The gasifier and PCD operations were stable in both enriched air and 100 percent oxygen blown modes. The oxygen concentration was slowly increased during the first transition to full oxygen-blown operations. Subsequent transitions from air to oxygen blown could be completed in less than 15 minutes. Oxygen-blown operations produced the highest synthesis gas heating value to date, with a projected synthesis gas heating value averaging 175 Btu/scf. Carbon conversions averaged 93 percent, slightly lower than carbon conversions achieved during air-blown gasification.

  6. On present situation of radioactive waste management and exposure of workers in nuclear reactor facilities for commercial power generation in fiscal 1988

    International Nuclear Information System (INIS)

    1989-01-01

    The article summarizes the contents of some reports including the Report on Radiation Management in 1988 that were submitted by the operators of nuclear reactor facilities for commercial power generation according to the requirements specified in the Law Concerning Regulation on Nuclear Material, Nuclear Fuel and Nuclear Reactor. According to these reports, the annual radiation release in all nuclear power generation plants was well below the radiation release limits set up in the report 'On Guidelines for Target Dose in Areas around Light Water Reactor Facilities for Power Generation'. Data submitted also show that there are no significant problems with the management of radioactive solid waste. In all nuclear generation plants, the personal exposure of workers is below the permissible exposure dose specified in law. The Agency of Natural Resources and Energy is planned to further promote the development of advanced techniques for automatization and remote control of light water reactors and to provide effective guidance to electrical contractors for positive radiation management. (N.K.)

  7. 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.

  8. Site Characterization Report ORGDP Diffusion Facilities Permanent Shutdown K-700 Power House and K-27 Switch Yard/Switch House

    Energy Technology Data Exchange (ETDEWEB)

    Thomas R.J., Blanchard R.D.

    1988-06-13

    The K-700 Power House area, initially built to supply power to the K-25 gaseous diffusion plant was shutdown and disassembled in the 1960s. This shutdown was initiated by TVA supplying economical power to the diffusion plant complex. As a result of world wide over production of enriched, reactor grade U{sup 235}, the K-27 switch yard and switch house area was placed in standby in 1985. Subsequently, as the future production requirements decreased, the cost of production increased and the separation technologies for other processes improved, the facility was permanently shutdown in December, 1987. This Site Characterization Report is a part of the FY-88 engineering Feasibility Study for placing ORGDP Gaseous Diffusion Process facilities in 'Permanent Shutdown'. It is sponsored by the Department of Energy through Virgil Lowery of Headquarters--Enrichment and through Don Cox of ORO--Enrichment Operations. The primary purpose of these building or site characterization reports is to document, quantify, and map the following potential problems: Asbestos; PCB containing fluids; Oils, coolants, and chemicals; and External contamination. With the documented quantification of the concerns (problems) the Engineering Feasibility Study will then proceed with examining the potential solutions. For this study, permanent shutdown is defined as the securing and/or conditioning of each facility to provide 20 years of safe service with minimal expenditures and, where feasible, also serving DOE's needs for long-term warehousing or other such low-risk use. The K-700 power house series of buildings were either masonry construction or a mix of masonry and wood. The power generating equipment was removed and sold as salvage in the mid 1960s but the buildings and auxiliary equipment were left intact. The nine ancillary buildings in the power house area use early in the Manhattan Project for special research projects, were left intact minus the original special equipment

  9. Conceptual study of nuclear power generation facilities life-cycle support versatile engineering database. Procedure of development and consideration of fundamental functions

    International Nuclear Information System (INIS)

    Endo, Hidetoshi

    2009-05-01

    International Atomic Energy Agency (IAEA) stands out the activity of the knowledge management of nuclear safety and the movement to introduce the idea of the life cycle management into the quality control of maintenance of the nuclear power generation facilities to assure the knowledge preservation and to succeed the technology of facilities. Japan Atomic Energy Agency (JAEA) also has such activities as the knowledge preservation of research and development, and related information. The facilities' performance reliability can be easily checked with the technology of data processing in the general industry and the results of the knowledge repository, transmitting technology and knowledge management by referring to the information and knowledge if the information and knowledge at each step of the life-cycle of facilities can be built. This report shows the strategy of the construction of the engineering database to support the life cycle of facilities and the basic function of the management system. (author)

  10. Prevention of significant deterioration permit application for the Fueled Clad Fabrication System, the Radioisotope Power Systems Facility, and the Fuel Assembly Area

    Energy Technology Data Exchange (ETDEWEB)

    1989-08-01

    This New Source Review'' has been submitted by the US Department of Energy-Richland Operations Office (PO Box 550, Richland, Washington 99352), pursuant to WAC 173-403-050 and in compliance with the Department of Ecology Guide to Processing A Prevention Of Significant Deterioration (PSD) Permit'' for three new sources of radionuclide emissions at the Hanford Site in Washington State. The three new sources, the Fueled Clad Fabrication System (FCFS), the Radioisotope Power Systems Facility (RPSF), and the Fuel Assembly Area (FAA), will be located in one facility, the Fuels and Materials Examination Facility (FMEF) of the 400 Area. The FMEF was originally designed to provide for post-irradiation examination and fabrication of breeder reactor fuels. These FMEF missions were cancelled before the introduction of any fuel materials or any irradiated material. The current plans are to use the facility to fabricate power supplies for use in space applications and to produce Fast Flux Test Facility (FFTF) fuel and target assemblies. The FCFS and the RPSF will produce materials and assemblies for application in space. The FAA project will produce FFTF fuel and target assemblies. The FCFS and the RPSF will share the same building, stack, and, in certain cases, the same floor space. Given this relationship, these systems will be dealt with separately to the extent possible. The FAA is a comparatively independent operation though it will share the FMEF complex.

  11. Initial high-power testing of the ATF [Advanced Toroidal Facility] ECH [electron cyclotron heating] system

    International Nuclear Information System (INIS)

    White, T.L.; Bigelow, T.S.; Kimrey, H.D. Jr.

    1987-01-01

    The Advanced Toroidal Facility (ATF) is a moderate aspect ratio torsatron that will utilize 53.2 GHz 200 kW Electron Cyclotron Heating (ECH) to produce nearly current-free target plasmas suitable for subsequent heating by strong neutral beam injection. The initial configuration of the ECH system from the gyrotron to ATF consists of an optical arc detector, three bellows, a waveguide mode analyzer, two TiO 2 mode absorbers, two 90 0 miter bends, two waveguide pumpouts, an insulating break, a gate valve, and miscellaneous straight waveguide sections feeding a launcher radiating in the TE 02 mode. Later, a focusing Vlasov launcher will be added to beam the ECH power to the saddle point in ATF magnetic geometry for optimum power deposition. The ECH system has several unique features; namely, the entire ECH system is evacuated, the ECH system is broadband, forward power is monitored by a newly developed waveguide mode analyzer, phase correcting miter bends will be employed, and the ECH system will be capable of operating short pulse to cw. Initial high-power tests show that the overall system efficiency is 87%. The waveguide mode analyzer shows that the gyrotron mode output consists of 13% TE 01 , 82.6% TE 02 , 2.5% TE 03 , and 1.9% TE 04 . 4 refs

  12. A facility for the testing and repair of primary collectors of steam generators at WWER nuclear power plants

    International Nuclear Information System (INIS)

    Herman, M.; Kuna, M.

    1990-01-01

    A facility labelled ZOKPG-1 has been developed for in-service inspection and repair of steam generator collectors in WWER-440 nuclear power plants. The facility makes possible visual, capillary, luminescence and ultrasonic inspection and eddy current testing of the internal surface, base material and welded joints of the collector. The repair modules of the ZOKPG-1 manipulator enable electroerosive elimination of surface defects of the material and local electrochemical decontamination of the internal surfaces. The manipulator can be operated at temperatures up to 40 degC, humidity up to 100%, and in conditions of radiation load up to 15 mGy/h and of surface contamination on the order of 100 Bq/cm 2 . (Z.M.). 16 figs

  13. Supplemental information for a notice of construction for the Fueled Clad Fabrication System, the Radioisotope Power Systems Facility, and the Fuel Assembly Area

    Energy Technology Data Exchange (ETDEWEB)

    1989-08-01

    This ''Notice of Construction'' has been submitted by the US Department of Energy-Richland Operations Office (P.O. Box 550, Richland, Washington 99352), pursuant to WAC 402-80-070, for three new sources of radionuclide emissions at the Hanford Site in Washington State (Figure 1). The three new sources, the Fueled Clad Fabrication System (FCFS) the Radioisotope Power Systems Facility (RPSF) and the Fuel Assembly Area (FAA) will be located in one facility, the Fuels and materials Examination Facility (FMEF) of the 400 Area. The FMEF was originally designed to provide for post- irradiation examination and fabrication of breeder reactor fuels. These FMEF missions were cancelled before the introduction of any fuel materials or any irradiated material. The current plans are to use the facility to fabricate power supplies to be used in space applications and to produce Fast Flux Test Facility (FFTF) fuel and target assemblies. The FCFS and the RPSF will produce materials and assemblies for application in space. The FAA project will produce FFTF fuel and target assemblies. The FCFS and the RPSF will share the same building, stack, and, in certain cases, the same floor space. Given this relationship, to the extent possible, these systems will be dealt with separately. The FAA is a comparatively independent operation though it will share the FMEF complex.

  14. The Text of the Agreement Between the Agency and Argentina for the Application of Safeguards to the Embalse Power Reactor Facility

    International Nuclear Information System (INIS)

    1975-01-01

    The text of the Agreement between the Agency and the Government of the Republic of Argentina for the Application of Safeguards to the Embalse Power Reactor Facility is reproduced in this document for the information of all Members

  15. The Text of the Agreement between the Agency and Argentina for the Application of Safeguards to the Atucha Power Reactor Facility

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1973-01-25

    The text of the Agreement between the Agency and the Government of the Republic of Argentina for the Application of Safeguards to the Atucha Power Reactor Facility is reproduced in this document for the information of all Members.

  16. The Texts of the Instruments Concerning the Agency's Assistance to Mexico in Establishing a Nuclear Power Facility

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1974-04-05

    The texts of the Supply Agreement between the Agency and the Governments of Mexico and the United States of America, and of the Project Agreement between the Agency and the Government of Mexico concerning the Agency's assistance to that Government in establishing a nuclear power facility, are reproduced herein for the information of all Members. The Agreements entered into force on 12 February 1974, pursuant to Articles VIII and IX respectively.

  17. The Texts of the Instruments Concerning the Agency's Assistance to Mexico in Establishing a Nuclear Power Facility

    International Nuclear Information System (INIS)

    1974-01-01

    The texts of the Supply Agreement between the Agency and the Governments of Mexico and the United States of America, and of the Project Agreement between the Agency and the Government of Mexico concerning the Agency's assistance to that Government in establishing a nuclear power facility, are reproduced herein for the information of all Members. The Agreements entered into force on 12 February 1974, pursuant to Articles VIII and IX respectively.

  18. Nuclear power generation facility

    International Nuclear Information System (INIS)

    Kubo, Mitsuji.

    1996-01-01

    Main steams are introduced from a moisture separation device for removing moisture content of the main steams to a low pressure turbine passing through a cross-around pipe. A condensate desalter comprising a mixed floor-type desalting tower using granular ion exchange resins is disposed at the downstream of the main condensator by way of condensate pipelines, and a feedwater heater is disposed at the downstream. Structural members of the main condensator are formed by weather proof steels. Low alloy steels are used partially or entirely for the cross-around pipe, gas extraction pipelines, heat draining pipelines, inner structural members other than pipelines in the feedwater heater, and the body and the inner structural members of the moisture separator. Titanium or a titanium alloy is used for the pipelines in the main condensator. With such a constitution, BWR type reactor facilities, in which the concentration of cruds inflown to the condensate cleanup system is reduced to simplify the condensate cleanup device can be obtained. (I.N.)

  19. The Great Plains Wind Power Test Facility

    Energy Technology Data Exchange (ETDEWEB)

    Schroeder, John [Texas Tech Univ., Lubbock, TX (United States)

    2014-01-30

    This multi-year, multi-faceted project was focused on the continued development of a nationally-recognized facility for the testing, characterization, and improvement of grid-connected wind turbines, integrated wind-water desalination systems, and related educational and outreach topics. The project involved numerous faculty and graduate students from various engineering departments, as well as others from the departments of Geosciences (in particular the Atmospheric Science Group) and Economics. It was organized through the National Wind Institute (NWI), which serves as an intellectual hub for interdisciplinary and transdisciplinary research, commercialization and education related to wind science, wind energy, wind engineering and wind hazard mitigation at Texas Tech University (TTU). Largely executed by an academic based team, the project resulted in approximately 38 peer-reviewed publications, 99 conference presentations, the development/expansion of several experimental facilities, and two provisional patents.

  20. ARC: A compact, high-field, disassemblable fusion nuclear science facility and demonstration power plant

    Science.gov (United States)

    Sorbom, Brandon; Ball, Justin; Palmer, Timothy; Mangiarotti, Franco; Sierchio, Jennifer; Bonoli, Paul; Kasten, Cale; Sutherland, Derek; Barnard, Harold; Haakonsen, Christian; Goh, Jon; Sung, Choongki; Whyte, Dennis

    2014-10-01

    The Affordable, Robust, Compact (ARC) reactor conceptual design aims to reduce the size, cost, and complexity of a combined Fusion Nuclear Science Facility (FNSF) and demonstration fusion pilot power plant. ARC is a 270 MWe tokamak reactor with a major radius of 3.3 m, a minor radius of 1.1 m, and an on-axis magnetic field of 9.2 T. ARC has Rare Earth Barium Copper Oxide (REBCO) superconducting toroidal field coils with joints to allow disassembly, allowing for removal and replacement of the vacuum vessel as a single component. Inboard-launched current drive of 25 MW LHRF power and 13.6 MW ICRF power is used to provide a robust, steady state core plasma far from disruptive limits. ARC uses an all-liquid blanket, consisting of low pressure, slowly flowing Fluorine Lithium Beryllium (FLiBe) molten salt. The liquid blanket acts as a working fluid, coolant, and tritium breeder, and minimizes the solid material that can become activated. The large temperature range over which FLiBe is liquid permits blanket operation at 800-900 K with single phase fluid cooling and allows use of a high-efficiency Brayton cycle for electricity production in the secondary coolant loop.

  1. 18 CFR 154.307 - Joint facilities.

    Science.gov (United States)

    2010-04-01

    ... 18 Conservation of Power and Water Resources 1 2010-04-01 2010-04-01 false Joint facilities. 154... Changes § 154.307 Joint facilities. The Statements required by § 154.312 must show all costs (investment... in the subject rate change and are associated with joint facilities. The methods used in making such...

  2. Regulation for delivery of subsidies for urgent safety measures for atomic power generating facilities

    International Nuclear Information System (INIS)

    1984-01-01

    The regulations provide for subsidies for the emergency measures taken by the prefecture concerned in preparation for a major accident in a nuclear power generating, etc. facility. These activities include an emergency communication network, emergency medical care, personnel education, and outfitting of emergency personnel. The contents are as follows: terms of subsidy allocations, the sum of a subsidy allocation, applications for subsidies, determination of subsidy allocations, withdrawal of applications the conditions attached to the allocations, a report on the work proceedings, a report on the results, confirmation on the sum of the subsidies, withdrawal of the decision for subsidies, limitations for the disposal of the properties, etc. (Mori, K.)

  3. Robins Air Force Base Solar Cogeneration Facility design

    Energy Technology Data Exchange (ETDEWEB)

    Pierce, B.L.; Bodenschatz, C.A.

    1982-06-01

    A conceptual design and a cost estimate have been developed for a Solar Cogeneration Facility at Robins Air Force Base. This demonstration solar facility was designed to generate and deliver electrical power and process steam to the existing base distribution systems. The facility was to have the potential for construction and operation by 1986 and make use of existing technology. Specific objectives during the DOE funded conceptual design program were to: prepare a Solar Cogeneration Facility (overall System) Specification, select a preferred configuration and develop a conceptual design, establish the performance and economic characteristics of the facility, and prepare a development plan for the demonstration program. The Westinghouse team, comprised of the Westinghouse Advanced Energy Systems Division, Heery and Heery, Inc., and Foster Wheeler Solar Development Corporation, in conjunction with the U.S. Air Force Logistics Command and Georgia Power Company, has selected a conceptual design for the facility that will utilize the latest DOE central receiver technology, effectively utilize the energy collected in the application, operate base-loaded every sunny day of the year, and be applicable to a large number of military and industrial facilities throughout the country. The design of the facility incorporates the use of a Collector System, a Receiver System, an Electrical Power Generating System, a Balance of Facility - Steam and Feedwater System, and a Master Control System.

  4. Power fluctuation reduction methodology for the grid-connected renewable power systems

    Science.gov (United States)

    Aula, Fadhil T.; Lee, Samuel C.

    2013-04-01

    This paper presents a new methodology for eliminating the influence of the power fluctuations of the renewable power systems. The renewable energy, which is to be considered an uncertain and uncontrollable resource, can only provide irregular electrical power to the power grid. This irregularity creates fluctuations of the generated power from the renewable power systems. These fluctuations cause instability to the power system and influence the operation of conventional power plants. Overall, the power system is vulnerable to collapse if necessary actions are not taken to reduce the impact of these fluctuations. This methodology aims at reducing these fluctuations and makes the generated power capability for covering the power consumption. This requires a prediction tool for estimating the generated power in advance to provide the range and the time of occurrence of the fluctuations. Since most of the renewable energies are weather based, as a result a weather forecast technique will be used for predicting the generated power. The reduction of the fluctuation also requires stabilizing facilities to maintain the output power at a desired level. In this study, a wind farm and a photovoltaic array as renewable power systems and a pumped-storage and batteries as stabilizing facilities are used, since they are best suitable for compensating the fluctuations of these types of power suppliers. As an illustrative example, a model of wind and photovoltaic power systems with battery energy and pumped hydro storage facilities for power fluctuation reduction is included, and its power fluctuation reduction is verified through simulation.

  5. Indicators System Creation For The Energy Efficiency Benchmarking Of Municipal Power System Facilities

    Directory of Open Access Journals (Sweden)

    Davydenko L.V.

    2015-04-01

    Full Text Available The issues of the dataware of the comparative analysis procedure (benchmarking for municipal power system facilities energy efficiency level estimation with a view of the hierarchical structure of the heat supply system are considered. The aim of the paper is the system of indicators formation for characterizing the efficiency of energy usage as on objects on lowest so on highest levels of power systems, proceeding from features of their functioning. Benchmarking methodology allows carrying out the estimation of energy efficiency level on the base of a plurality of parameters without their generalization in one indicator, but requires ensuring their comparability. Using the methodology of available statistical information that did not require deep specification and additional inspection structuring objectives and tasks of energy efficiency estimation problem has been proposed for ensuring the opportunity of benchmarking procedure implementation. This makes it possible to form the subset of indicators that ensure enough specification of the object of study, taking into account the degree of abstraction for every hierarchical level or sub problem. For a comparative analysis of energy using efficiency in municipal power systems at the highest levels of the hierarchy a plurality of indicators of the energy efficiency has been formed. Indicators have been determined with consideration of the structural elements of heat supply systems, but allowing taking into account the efficiency of the initial state of the objects, their functioning, and the questions of energy resources accounting organization. Usage of the proposed indicators provides implementation of energy using efficiency monitoring in the municipal power system and allows getting complete overview of the problem.

  6. Emergency power systems at nuclear power plants

    International Nuclear Information System (INIS)

    1982-01-01

    This Guide applies to nuclear power plants for which the total power supply comprises normal power supply (which is electric) and emergency power supply (which may be electric or a combination of electric and non-electric). In its present form the Guide provides general guidance for all types of emergency power systems (EPS) - electric and non-electric, and specific guidance (see Appendix A) on the design principles and the features of the emergency electric power system (EEPS). Future editions will include a second appendix giving specific guidance on non-electric power systems. Section 3 of this Safety Guide covers information on considerations that should be taken into account relative to the electric grid, the transmission lines, the on-site electrical supply system, and other alternative power sources, in order to provide high overall reliability of the power supply to the EPS. Since the nuclear power plant operator does not usually control off-site facilities, the discussion of methods of improving off-site reliability does not include requirements for facilities not under the operator's control. Sections 4 to 11 of this Guide provide information, recommendations and requirements that would apply to any emergency power system, be it electric or non-electric

  7. Nuclear EMP induced chaos. [Effect of nuclear explosion on power and communication facilities

    Energy Technology Data Exchange (ETDEWEB)

    Dance, B

    1983-04-01

    It is anticipated that a single nuclear explosion, of adequate size, on the outside of the atmosphere would generate a pulse of sufficient intensity to damage communications equipment (including telephones, radio transmitters and receivers), and to disrupt main power supplies. This damage could be done by a very intense, short duration electro-magnetic pulse (EMP). The article discusses the generation and history of EMP, the test facilities that are needed for EMP test, and techniques that can be used to harden equipment against EMP. It is also important to protect extensive systems against EMP. The article points out that fibre-optics are very useful, because they are EMP resistant and a single fibre can also carry a very high data rate.

  8. Historical records of the electric power and cooling water systems for the experimental facilities in the I.P.P. (1964-1983)

    International Nuclear Information System (INIS)

    Kitajima, Miyoshi.

    1984-01-01

    Twenty years have passed, since experimental studies began in the IPP. This is a status report on the electric power and cooling water systems in this Institute. Historical records on consumption of the electric power and cooling water for experimental facilities are summarized, also. Valuable stories obtained through operation, control and periodic inspection of these systems are described, which will be helpful for construction of new systems in future. Finally problems on safety, reliability, and economy are commented. (author)

  9. Regulation of fuel cycle facilities in the UK

    International Nuclear Information System (INIS)

    Ascroft-Hutton, H.W.

    2001-01-01

    The UK has facilities for the production of uranium hexafluoride, its enrichment, conversion into fuel and for the subsequent reprocessing of irradiated fuel and closure of the fuel cycle. All of these facilities must be licensed under UK legislation. HM Nuclear Installations Inspectorate has delegated powers to issue the licence and to attach any conditions it considers necessary in the interests of safety. The fuel cycle facilities in the UK have been licensed since 1971. This paper describes briefly the UK nuclear regulatory framework and the fuel cycle facilities involved. It considers the regulatory practices adopted together with similarities and differences between regulation of fuel cycle facilities and power reactors. The safety issues associated with the fuel cycle are discussed and NII's regulatory strategy for these facilities is set out. (author)

  10. Test facility for the evaluation of microwave transmission components

    International Nuclear Information System (INIS)

    Fong, C.G.; Poole, B.R.

    1985-01-01

    A Low Power Test Facility (LPTF) was developed to evaluate the performance of Electron Cyclotron Resonance Heating (ECRH) microwave transmission components for the Mirror Fusion Test Facility (MFTF-B). The facility generates 26 to 60 GHz in modes of TE 01 , TE 02 , or TE 03 launched at power levels of 1/2 milliwatt. The propagation of the rf as it radiates from either transmitting or secondary reflecting microwave transmission components is recorded by a discriminating crystal detector mechanically manipulated at constant radius in spherical coordinates. The facility is used to test, calibrate, and verify the design of overmoded, circular waveguide components, quasi-optical reflecting elements before high power use. The test facility consists of microwave sources and metering components, such as VSWR, power and frequency meters, a rectangular TE 10 to circular TE 01 mode transducer, mode filter, circular TE 01 to 2.5 in. diameter overmoded waveguide with mode converters for combination of TE 01 to TE 03 modes. This assembly then connects to a circular waveguide launcher or the waveguide component under test

  11. Childhood leukemia around nuclear facilities

    International Nuclear Information System (INIS)

    1991-01-01

    This Information Bulletin highlights the conclusion made from an Atomic Energy Control Board of Canada (AECB) study on the incidence of childhood leukemia near nuclear facilities. All of the locations with the nuclear facilities are located in Ontario, the nuclear generating stations at Pickering and Bruce; the uranium mines and mills in Elliot Lake; the uranium refining facility in Port Hope; and nuclear research facilities located at Chalk River plus the small nuclear power plant in Rolphton. Two conclusions are drawn from the study: 1) while the rate of childhood leukemias made be higher or lower than the provincial average, there is no statistical evidence that the difference is due to anything but the natural variation in the occurrence of the disease; and 2) the rate of occurrence of childhood leukemia around the Pickering nuclear power station was slightly greater than the Ontario average both before and after the plant opened, but this, too , could be due to the natural variation

  12. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume III. Resources and fuel cycle facilities

    International Nuclear Information System (INIS)

    1980-06-01

    The ability of uranium supply and the rest of the nuclear fuel cycle to meet the demand for nuclear power is an important consideration in future domestic and international planning. Accordingly, the purpose of this assessment is to evaluate the adequacy of potential supply for various nuclear resources and fuel cycle facilities in the United States and in the world outside centrally planned economy areas (WOCA). Although major emphasis was placed on uranium supply and demand, material resources (thorium and heavy water) and facility resources (separative work, spent fuel storage, and reprocessing) were also considered

  13. Improvement of irradiation facilities performance in JMTR

    International Nuclear Information System (INIS)

    Kanno, Masaru; Sakurai, Susumu; Honma, Kenzo; Sagawa, Hisashi; Nakazaki, Chousaburo

    1999-01-01

    Various kinds of irradiation facilities are installed in the JMTR for the purpose of irradiation tests on fuels and materials and of producing radioisotopes. The irradiation facilities have been improved so far at every opportunity of new irradiation requirements and of renewing them which reached the design lifetime. Of these irradiation facilities, improvements of the power ramping test facility (BOCA/OSF-1 facility) and the hydraulic rabbit No.2 (HR-2 facility) are described here. (author)

  14. The International Remote Monitoring Project: Results of the Swedish Nuclear Power Facility field trial

    International Nuclear Information System (INIS)

    Johnson, C.S.; af Ekenstam, G.; Sallstrom, M.

    1995-01-01

    The Swedish Nuclear Power Inspectorate (SKI) and the US Department of Energy (DOE) sponsored work on a Remote Monitoring System (RMS) that was installed in August 1994 at the Barseback Works north of Malmo, Sweden. The RMS was designed to test the front end detection concept that would be used for unattended remote monitoring activities. Front end detection reduces the number of video images recorded and provides additional sensor verification of facility operations. The function of any safeguards Containment and Surveillance (C/S) system is to collect information which primarily is images that verify the operations at a nuclear facility. Barseback is ideal to test the concept of front end detection since most activities of safeguards interest is movement of spent fuel which occurs once a year. The RMS at Barseback uses a network of nodes to collect data from microwave motion detectors placed to detect the entrance and exit of spent fuel casks through a hatch. A video system using digital compression collects digital images and stores them on a hard drive and a digital optical disk. Data and images from the storage area are remotely monitored via telephone from Stockholm, Sweden and Albuquerque, NM, USA. These remote monitoring stations operated by SKI and SNL respectively, can retrieve data and images from the RMS computer at the Barseback Facility. The data and images are encrypted before transmission. This paper presents details of the RMS and test results of this approach to front end detection of safeguard activities

  15. The National Carbon Capture Center at the Power Systems Development Facility

    Energy Technology Data Exchange (ETDEWEB)

    Mosser, Morgan [Southern Company Services, Inc., Wilsonville, AL (United States)

    2012-12-31

    The Power Systems Development Facility (PSDF) is a state-of-the-art test center sponsored by the U.S. Department of Energy and dedicated to the advancement of clean coal technology. In addition to the development of high efficiency coal gasification processes, the PSDF features the National Carbon Capture Center (NCCC) to promote new technologies for CO2 capture from coal-derived syngas and flue gas. The NCCC includes multiple, adaptable test skids that allow technology development of CO2 capture concepts using coal-derived syngas and flue gas in industrial settings. Because of the ability to operate under a wide range of flow rates and process conditions, research at the NCCC can effectively evaluate technologies at various levels of maturity and accelerate their development path to commercialization. During the calendar year 2012 portion of the Budget Period Four reporting period, efforts at the NCCC focused on testing of pre- and post-combustion CO2 capture processes and gasification support technologies. Preparations for future testing were on-going as well, and involved facility upgrades and collaboration with numerous technology developers. In the area of pre-combustion, testing was conducted on a new water-gas shift catalyst, a CO2 solvent, and gas separation membranes from four different technology developers, including two membrane systems incorporating major scale-ups. Post-combustion tests involved advanced solvents from three major developers, a gas separation membrane, and two different enzyme technologies. An advanced sensor for gasification operation was evaluated, operation with biomass co-feeding with coal under oxygen-blown conditions was achieved, and progress continued on refining several gasification support technologies.

  16. The National Carbon Capture Center at the Power Systems Development Facility

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2014-07-14

    The Power Systems Development Facility (PSDF) is a state-of-the-art test center sponsored by the U.S. Department of Energy (DOE) and dedicated to the advancement of clean coal technology. In addition to the development of high efficiency coal gasification processes, the PSDF features the National Carbon Capture Center (NCCC) to promote new technologies for CO2 capture from coal-derived flue gas and syngas. The NCCC includes multiple, adaptable test skids that allow technology development of CO2 capture concepts using coal-derived flue gas and syngas in industrial settings. Because of the ability to operate under a wide range of flow rates and process conditions, research at the NCCC can effectively evaluate technologies at various levels of maturity and accelerate their development paths to commercialization. During the calendar year 2013 portion of the Budget Period Four reporting period, efforts at the NCCC focused on post-combustion CO2 capture, gasification, and pre-combustion CO2 capture technology testing. Preparations for future testing were on-going as well, and involved facility upgrades and collaboration with numerous technology developers. In the area of post-combustion, testing was conducted on an enzyme-based technology, advanced solvents from two major developers, and a gas separation membrane. During the year, the gasification process was operated for three test runs, supporting development of water-gas shift and COS hydrolysis catalysts, a mercury sorbent, and several gasification support technologies. Syngas produced during gasification operation was also used for pre-combustion capture technologies, including gas separation membranes from three different technology developers, a CO2 sorbent, and CO2 solvents.

  17. 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.

  18. SERC Central Laser Facility annual report 1992

    International Nuclear Information System (INIS)

    1992-01-01

    In this 1992 Annual Report to the Laser Facility Committee of the Science and Engineering Research Council, the Central Laser Facility at Rutherford Appleton Laboratory, technical progress is described and mid-term organizational goals outlined. Outstanding among recent achievements is the work on plasma heating being undertaken on the Sprite facility using the ultra-bright KrF laser pumped Raman beams. Two-beam operation at power levels approaching 2 TW in 10 ps are hoped for. On a four year timescale the Titania system will provide four Raman beams of exceptional brightness and power up to 20TW in 10ps. The other high power laser facility, Vulcan is also producing exciting work. Progress in nanosecond studies using Raman spectroscopy have produced the first Raman spectrum of solvated Buckmister fullerene and direct observation of the separation of germinate ion pairs, as well as information on the behaviour of a single base in an oligonuclide chain. Phase boundaries for the solidification of a two dimensional electron fluid have been determined in a Gallium Arsenide heterojunction. Despite staff number attrition, operation and development of the facilities have continued successfully. (UK)

  19. 7 CFR 1710.303 - Power cost studies-power supply borrowers.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 11 2010-01-01 2010-01-01 false Power cost studies-power supply borrowers. 1710.303... AND GUARANTEES Long-Range Financial Forecasts § 1710.303 Power cost studies—power supply borrowers. (a... facilities shall be supported by a power cost study to demonstrate that the proposed generation and...

  20. Nuclear fuel treatment facility for 'Mutsu'

    International Nuclear Information System (INIS)

    Kanazawa, Toshio; Fujimura, Kazuo; Horiguchi, Eiji; Kobayashi, Tetsuji; Tamekiyo, Yoshizou

    1989-01-01

    A new fixed mooring harbor in Sekinehama and surrounding land facilities to accommodate a test voyage for the nuclear-powered ship 'Mutsu' in 1990 were constructed by the Japan Atomic Energy Research Institute. Kobe Steel took part in the construction of the nuclear fuel treatment process in various facilities, beginning in October, 1988. This report describes the outline of the facility. (author)

  1. Environmental assessment: South microwave communication facilities

    Energy Technology Data Exchange (ETDEWEB)

    1989-06-01

    Western Area Power Administration (Western) is proposing to construct, operate, and maintain eight microwave repeater stations in southwestern Colorado, southeastern Utah, and northern Arizona, in order to meet the minimum fade criteria established by the Western Systems Coordinating Council (WSCC) for the operation and protection of electric power systems. The proposed microwave facilities would increase the reliability of communication. This environmental assessment (EA) describes the existing environmental conditions and the impacts from construction of the eight microwave communication facilities. The EA was prepared in compliance with the National Environmental Policy Act of 1969, the Council on Environmental Quality Regulations (40 CFR 1500-1508), and the Department of Energy Guidelines (52 FR 47662, December 15, 1987). The proposed project would consist of constructing eight microwave facilities, each of which would include a self-supported lattice tower, an equipment building, a propane tank, distribution lines to provide electric power to the sites, and access roads to the sites. The facilities would be constructed in San Miguel and Montezuma Counties in Colorado, San Juan County, Utah, and Navajo, Apache, Coconino, and Yavapai Counties in Arizona. 20 refs., 2 figs., 2 tabs.

  2. The Burning Plasma Experiment conventional facilities

    International Nuclear Information System (INIS)

    Commander, J.C.

    1991-01-01

    The Burning Program Plasma Experiment (BPX) is phased to start construction of conventional facilities in July 1994, in conjunction with the conclusion of the Tokamak Fusion Test Reactor (TFTR) project. This paper deals with the conceptual design of the BPX Conventional Facilities, for which Functional and Operational Requirements (F ampersand ORs) were developed. Existing TFTR buildings and utilities will be adapted and used to satisfy the BPX Project F ampersand ORs to the maximum extent possible. However, new conventional facilities will be required to support the BPX project. These facilities include: The BPX building; Site improvements and utilities; the Field Coil Power Conversion (FCPC) building; the TFTR modifications; the Motor Generation (MG) building; Liquid Nitrogen (LN 2 ) building; and the associated Instrumentation and Control (I ampersand C) systems. The BPX building will provide for safe and efficient shielding, housing, operation, handling, maintenance and decontamination of the BPX and its support systems. Site improvements and utilities will feature a utility tunnel which will provide a space for utility services--including pulse power duct banks and liquid nitrogen coolant lines. The FCPC building will house eight additional power supplied for the Toroidal Field (TF) coils. The MG building will house the two MG sets larger than the existing TFTR MG sets. This paper also addresses the conventional facility cost estimating methodology and the rationale for the construction schedule developed. 6 figs., 1 tab

  3. High power fast ramping power supplies

    Energy Technology Data Exchange (ETDEWEB)

    Marneris,I.; Bajon, E.; Bonati, R.; Sandberg, J.; Roser, T.; Tsoupas, N.

    2009-05-04

    Hundred megawatt level fast ramping power converters to drive proton and heavy ion machines are under research and development at accelerator facilities in the world. This is a leading edge technology. There are several topologies to achieve this power level. Their advantages and related issues will be discussed.

  4. Results of gap conductance tests in the power burst facility

    International Nuclear Information System (INIS)

    Garner, R.W.; Sparks, D.T.

    1977-01-01

    Light water reactor (LWR) fuel rod behavior studies are being conducted by the Thermal Fuels Behavior Program of EG and G Idaho, Inc. These studies are being performed under contract to the Energy Research and Development Adminstration at the Idaho National Engineering Laboratory (INEL), as part of the Nuclear Regulatory Commission's Water Reactor Safety Research Fuel Behavior Program. Experimental data for verification of analytical models developed to predict light water nuclear fuel rod behavior under normal and postulated accident conditions are being obtained from a variety of in-reactor and out-of-reactor experiments. This paper summarizes the results of tests performed in the Power Burst Facility (PBF) to obtain data from which the thermal response, gap conductance, and stored energy of LWR fuel rods can be determined. Primary objectives of the PBF gap conductance test program are (a) to obtain data on a variety of pressurized water reactor (PWR) and boiling water reactor (BWR) fuel rod designs, under a wide range of operating conditions, from which gap conductance values can be determined and (b) to evaluate experimentally the power oscillation method for measuring the gap conductance and thermal response of a fresh or burned LWR fuel rod. Tests have been performed with both irradiated and unirradiated PWR-type fuel and with fresh BWR-type fuel rods. Some PWR rod test results are described, and the thermal response data from BWR rod tests are discussed in greater detail. Comparisons are made of gap conductance values determined by the tests with analytically calculated values using the Fuel Rod Analysis Program-Transient (FRAP-T) computer code. These comparisons provide insight into both the experimental measurements methods and the validity of the gap conductance models

  5. Potentials of wind power

    International Nuclear Information System (INIS)

    Bezrukikh, P.P.; Bezrukikh, P.P.

    2000-01-01

    The ecological advantages of the wind power facilities (WPF) are considered. The possibilities of small WPF, generating the capacity from 40 W up to 10 kW, are discussed. The basic technical data on the national and foreign small WPF are presented. The combined wind power systems are considered. Special attention is paid to the most perspective wind-diesel systems, which provide for all possible versions of the electro-power supply. Useful recommendations and information on the wind power engineering are given for those, who decided to build up a wind facility [ru

  6. Universal Drive Train Facility

    Data.gov (United States)

    Federal Laboratory Consortium — This vehicle drive train research facility is capable of evaluating helicopter and ground vehicle power transmission technologies in a system level environment. The...

  7. Concerning results of environmental monitoring around the reprocessing facilities of Power Reactor and Nuclear Fuel Development Corporation

    International Nuclear Information System (INIS)

    1989-01-01

    The Central Evaluation Expert Group for Environmental radiation Monitoring has been engaged in examinations of plants for and results of the environmental radiation monitoring performed by Power Reactor and Nuclear Fuel Development Corporation around its reprocessing facilities. The present report outlines an examination of the results of monitoring carried out in 1987 (January to December). It is concluded that the methods used for the monitoring and its technical level are satisfactory in meeting the objectives of the monitoring plans. Expept for tritium in seawater, the level of radiations stays within the normal variation determined based on preliminary measurements of the background radiation. The procedure used for the calculation of exposure dose is also satisfactory in meeting the requirements specified in the monitoring plants. It is confirmed that the exposure dose of the residents around the facilities is well below the permissible exposure dose limite specified in law. (Nogami. K.)

  8. Scaling laws between population and facility densities.

    Science.gov (United States)

    Um, Jaegon; Son, Seung-Woo; Lee, Sung-Ik; Jeong, Hawoong; Kim, Beom Jun

    2009-08-25

    When a new facility like a grocery store, a school, or a fire station is planned, its location should ideally be determined by the necessities of people who live nearby. Empirically, it has been found that there exists a positive correlation between facility and population densities. In the present work, we investigate the ideal relation between the population and the facility densities within the framework of an economic mechanism governing microdynamics. In previous studies based on the global optimization of facility positions in minimizing the overall travel distance between people and facilities, it was shown that the density of facility D and that of population rho should follow a simple power law D approximately rho(2/3). In our empirical analysis, on the other hand, the power-law exponent alpha in D approximately rho(alpha) is not a fixed value but spreads in a broad range depending on facility types. To explain this discrepancy in alpha, we propose a model based on economic mechanisms that mimic the competitive balance between the profit of the facilities and the social opportunity cost for populations. Through our simple, microscopically driven model, we show that commercial facilities driven by the profit of the facilities have alpha = 1, whereas public facilities driven by the social opportunity cost have alpha = 2/3. We simulate this model to find the optimal positions of facilities on a real U.S. map and show that the results are consistent with the empirical data.

  9. Catalytic Fuel Conversion Facility

    Data.gov (United States)

    Federal Laboratory Consortium — This facility enables unique catalysis research related to power and energy applications using military jet fuels and alternative fuels. It is equipped with research...

  10. DeBeNe Test Facilities for Fast Breeder Development

    International Nuclear Information System (INIS)

    Storz, R.

    1980-10-01

    This report gives an overview and a short description of the test facilities constructed and operated within the collaboration for fast breeder development in Germany, Belgium and the Netherlands. The facilities are grouped into Sodium Loops (Large Facilities and Laboratory Loops), Special Equipment including Hot Cells and Reprocessing, Test Facilities without Sodium, Zero Power Facilities and In-pile Loops including Irradiation Facilities

  11. Current summary of international extreme load design requirements for nuclear power plant facilities

    International Nuclear Information System (INIS)

    Stevenson, J.D.

    1980-01-01

    The development of extreme load design criteria both as to rate and depth within any national jurisdiction as applied to nuclear power plant design is a function of several factors. The prime factor is the number of nuclear power plant facilities which are operating, under construction or planned in a given country. The second most important factor seems to be the degree of development of a domestic independent nuclear steam system supplier, NSSS vendor. Finally, countries whose domestic NSSS firms are active in the export market appear to have more active criteria development programs or at least they appear more visible to the foreign observer. For the purposes of this paper, extreme loads are defined as those loads having probability of occurence less than 10 -1 /yr and whose occurence could result in radiological consequences in excess of those permitted by national health standards. The specific loads considered include earthquake, extreme wind (tornado), airplane crash, detonation, and high energy system rupture. The paper identifies five national centers for extreme load criteria development; Canada, Great Britian, USA, USSR, and West Germany with both France and Japan also about to appear as independent centers of criteria development. Criteria under development by each national center are discussed in detail. (orig.)

  12. Magnetohydrodynamics (MHD) Engineering Test Facility (ETF) 200 MWe power plant. Conceptual Design Engineering Report (CDER). Volume 1: Executive summary

    Science.gov (United States)

    1981-01-01

    Main elements of the design are identified and explained, and the rationale behind them was reviewed. Major systems and plant facilities are listed and discussed. Construction cost and schedule estimates are presented, and the engineering issues that should be reexamined are identified. The latest (1980-1981) information from the MHD technology program is integrated with the elements of a conventional steam power electric generating plant.

  13. Strategy selection for the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    2004-01-01

    As modern nuclear power programmes mature and large, commercial nuclear power plants and fuel cycle facilities approach the end of their useful life by reason of age, economics or change of policy on the use of nuclear power, new challenges associated with decommissioning and dismantling come to the fore. Politicians and the public may expect there to be a 'right answer' to the choice of strategy for a particular type of facility, or even all facilities. Both this seminar and wider experience show that this is not the case. Local factors and national political positions have a significant input and often result in widely differing strategy approaches to broadly similar decommissioning projects. All facility owners represented at the seminar were able to demonstrate a rational process for strategy selection and compelling arguments for the choices made. In addition to the papers that were presented, these proceedings include a summary of the discussions that took place. (author)

  14. A Swedish nuclear fuel facility and public acceptance

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Bengt A [ABB Atom (Sweden)

    1989-07-01

    For more than ten years the ABB Atom Nuclear Fuel Facility has gained a lot of public attention in Sweden. When the nuclear power debate was coming up in the middle of the seventies, the Nuclear Fuel Facility very soon became a spectacular object. It provided a possibility to bring factual information about nuclear power to the public. Today that public interest still exists. For ABB Atom the Facility works as a tool of information activities in several ways, as a solid base for ABB Atom company presentations. but also as a very practical demonstration of the nuclear power technology to the public. This is valid especially to satisfy the local school demand for a real life object complementary to the theoretical nuclear technology education. Beyond the fact that the Nuclear Fuel Facility is a very effective fuel production plant, it is not too wrong to see it as an important resource for education as well as a tool for improved public relations.

  15. A Swedish nuclear fuel facility and public acceptance

    International Nuclear Information System (INIS)

    Andersson, Bengt A.

    1989-01-01

    For more than ten years the ABB Atom Nuclear Fuel Facility has gained a lot of public attention in Sweden. When the nuclear power debate was coming up in the middle of the seventies, the Nuclear Fuel Facility very soon became a spectacular object. It provided a possibility to bring factual information about nuclear power to the public. Today that public interest still exists. For ABB Atom the Facility works as a tool of information activities in several ways, as a solid base for ABB Atom company presentations. but also as a very practical demonstration of the nuclear power technology to the public. This is valid especially to satisfy the local school demand for a real life object complementary to the theoretical nuclear technology education. Beyond the fact that the Nuclear Fuel Facility is a very effective fuel production plant, it is not too wrong to see it as an important resource for education as well as a tool for improved public relations

  16. Estimation of marginal costs at existing waste treatment facilities.

    Science.gov (United States)

    Martinez-Sanchez, Veronica; Hulgaard, Tore; Hindsgaul, Claus; Riber, Christian; Kamuk, Bettina; Astrup, Thomas F

    2016-04-01

    This investigation aims at providing an improved basis for assessing economic consequences of alternative Solid Waste Management (SWM) strategies for existing waste facilities. A bottom-up methodology was developed to determine marginal costs in existing facilities due to changes in the SWM system, based on the determination of average costs in such waste facilities as function of key facility and waste compositional parameters. The applicability of the method was demonstrated through a case study including two existing Waste-to-Energy (WtE) facilities, one with co-generation of heat and power (CHP) and another with only power generation (Power), affected by diversion strategies of five waste fractions (fibres, plastic, metals, organics and glass), named "target fractions". The study assumed three possible responses to waste diversion in the WtE facilities: (i) biomass was added to maintain a constant thermal load, (ii) Refused-Derived-Fuel (RDF) was included to maintain a constant thermal load, or (iii) no reaction occurred resulting in a reduced waste throughput without full utilization of the facility capacity. Results demonstrated that marginal costs of diversion from WtE were up to eleven times larger than average costs and dependent on the response in the WtE plant. Marginal cost of diversion were between 39 and 287 € Mg(-1) target fraction when biomass was added in a CHP (from 34 to 303 € Mg(-1) target fraction in the only Power case), between -2 and 300 € Mg(-1) target fraction when RDF was added in a CHP (from -2 to 294 € Mg(-1) target fraction in the only Power case) and between 40 and 303 € Mg(-1) target fraction when no reaction happened in a CHP (from 35 to 296 € Mg(-1) target fraction in the only Power case). Although average costs at WtE facilities were highly influenced by energy selling prices, marginal costs were not (provided a response was initiated at the WtE to keep constant the utilized thermal capacity). Failing to systematically

  17. Power Service Shops

    Data.gov (United States)

    Federal Laboratory Consortium — TVA's Power Service Shops provides expert repair and maintenance of power system components and large industrial equipment. With world-class maintenance facilities...

  18. GE PETtrace RF power failures related to poor power quality

    OpenAIRE

    Bender, B. R.; Erdahl, C. E.; Dick, D. W.

    2015-01-01

    Introduction Anyone who has ever overseen the installation of a new cyclotron is aware of the importance of addressing the numerous vendor-supplied site specifications prior to its arrival. If the site is not adequately prepared, the facility may face project cost overruns, poor cyclotron performance and unintended maintenance costs. Once a facility has identified the space, providing sufficient power is the next step. Every cyclotron vendor will provide you with a set of power specificati...

  19. Fusion Materials Irradiation Test Facility: a facility for fusion-materials qualification

    International Nuclear Information System (INIS)

    Trego, A.L.; Hagan, J.W.; Opperman, E.K.; Burke, R.J.

    1983-01-01

    The Fusion Materials Irradiation Test Facility will provide a unique testing environment for irradiation of structural and special purpose materials in support of fusion power systems. The neutron source will be produced by a deuteron-lithium stripping reaction to generate high energy neutrons to ensure damage similar to that of a deuterium-tritium neutron spectrum. The facility design is now ready for the start of construction and much of the supporting lithium system research has been completed. Major testing of key low energy end components of the accelerator is about to commence. The facility, its testing role, and the status and major aspects of its design and supporting system development are described

  20. Realities of proximity facility siting

    International Nuclear Information System (INIS)

    DeMott, D.L.

    1981-01-01

    Numerous commercial nuclear power plant sites have 2 to 3 reactors located together, and a group of Facilities with capabilities for fuel fabrication, a nuclear reactor, a storage area for spent fuel, and a maintenance area for contaminated equipment and radioactive waste storage are being designed and constructed in the US. The proximity of these facilities to each other provides that the ordinary flow of materials remain within a limited area. Interactions between the various facilities include shared resources such as communication, fire protection, security, medical services, transportation, water, electrical, personnel, emergency planning, transport of hazardous material between facilities, and common safety and radiological requirements between facilities. This paper will explore the advantages and disadvantages of multiple facilities at one site. Problem areas are identified, and recommendations for planning and coordination are discussed

  1. Magnetohydrodynamics (MHD) Engineering Test Facility (ETF) 200 MWe power plant. Conceptual Design Engineering Report (CDER). Volume 4: Supplementary engineering data

    Science.gov (United States)

    1981-01-01

    The reference conceptual design of the Magnetohydrodynamic Engineering Test Facility (ETF), a prototype 200 MWe coal-fired electric generating plant designed to demonstrate the commercial feasibility of open cycle MHD is summarized. Main elements of the design are identified and explained, and the rationale behind them is reviewed. Major systems and plant facilities are listed and discussed. Construction cost and schedule estimates, and identification of engineering issues that should be reexamined are also given. The latest (1980-1981) information from the MHD technology program are integrated with the elements of a conventional steam power electric generating plant. Supplementary Engineering Data (Issues, Background, Performance Assurance Plan, Design Details, System Design Descriptions and Related Drawings) is presented.

  2. Theoretical assessment of the maximum power point tracking efficiency of photovoltaic facilities with different converter topologies

    Energy Technology Data Exchange (ETDEWEB)

    Enrique, J.M.; Duran, E.; Andujar, J.M. [Departamento de Ingenieria Electronica, de Sistemas Informaticos y Automatica, Universidad de Huelva (Spain); Sidrach-de-Cardona, M. [Departamento de Fisica Aplicada, II, Universidad de Malaga (Spain)

    2007-01-15

    The operating point of a photovoltaic generator that is connected to a load is determined by the intersection point of its characteristic curves. In general, this point is not the same as the generator's maximum power point. This difference means losses in the system performance. DC/DC converters together with maximum power point tracking systems (MPPT) are used to avoid these losses. Different algorithms have been proposed for maximum power point tracking. Nevertheless, the choice of the configuration of the right converter has not been studied so widely, although this choice, as demonstrated in this work, has an important influence in the optimum performance of the photovoltaic system. In this article, we conduct a study of the three basic topologies of DC/DC converters with resistive load connected to photovoltaic modules. This article demonstrates that there is a limitation in the system's performance according to the type of converter used. Two fundamental conclusions are derived from this study: (1) the buck-boost DC/DC converter topology is the only one which allows the follow-up of the PV module maximum power point regardless of temperature, irradiance and connected load and (2) the connection of a buck-boost DC/DC converter in a photovoltaic facility to the panel output could be a good practice to improve performance. (author)

  3. 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)

  4. Lightning and surge protection of large ground facilities

    Science.gov (United States)

    Stringfellow, Michael F.

    1988-04-01

    The vulnerability of large ground facilities to direct lightning strikes and to lightning-induced overvoltages on the power distribution, telephone and data communication lines are discussed. Advanced electrogeometric modeling is used for the calculation of direct strikes to overhead power lines, buildings, vehicles and objects within the facility. Possible modes of damage, injury and loss are discussed. Some appropriate protection methods for overhead power lines, structures, vehicles and aircraft are suggested. Methods to mitigate the effects of transients on overhead and underground power systems as well as within buildings and other structures are recommended. The specification and location of low-voltage surge suppressors for the protection of vulnerable hardware such as computers, telecommunication equipment and radar installations are considered. The advantages and disadvantages of commonly used grounding techniques, such as single point, multiple and isolated grounds are compared. An example is given of the expected distribution of lightning flashes to a large airport, its buildings, structures and facilities, as well as to vehicles on the ground.

  5. FY 1999 report on the results of the joint study - project on the public facility use photovoltaic power generation field test; 1999 nendo kokyo shisetsunadoyo taiyoko hatsuden field test jigyo kyodo kenkyu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    In the field test, solar cell panels were installed on rooftop, and inverters were installed indoors. The electric power generated was connected at high pressure with electric installation of facilities and was also supplied to power equipment, lighting, air conditioning, etc. in facilities. The FY 1999 results were summarized. The installation of photovoltaic power generation facilities at 137 places and the results of the study were summarized in this report including a new university co-op building, Tokyo Metropolitan Advanced Technology Education Center, Suwano Center House of Fukushima prefecture, Environment Center of Saga prefecture, Educational Foundation Utsukushino Kindergarten, Hikarigaoka Park of Yamagata prefecture, Koiwai factory of Koiwai Dairy Products Co., Social Welfare Corporation Kameyama Ayumi Nursery School, etc. (NEDO)

  6. Recalculating the steady state conditions of the V-1000 zero-power facility at Kurchatov Institute using Monte Carlo and nodal diffusion codes

    Energy Technology Data Exchange (ETDEWEB)

    Sahlberg, Ville [VTT Technical Research Centre of Finland Ltd, VTT (Finland)

    2017-09-15

    Continuous-energy Monte Carlo reactor physics code Serpent 2 was used to model the critical steady state conditions measured in V-1000 zero-power critical facility at Kurchatov Institute (KI), Moscow in 1990-1992. The Serpent 2 results were compared to measurements and Serpent 2 was used to generate group constants for reactor dynamics code HEXTRAN. The results of a HEXTRAN calculation of the steady state were compared to Serpent 2. The relative power density distribution of the SERPENT2 calculations compared with the measurements was within the statistical accuracy. The comparison of HEXTRAN and Serpent 2 node-wise relative power density distributions showed an accuracy of ±10%.

  7. Earthquake engineering for nuclear facilities

    CERN Document Server

    Kuno, Michiya

    2017-01-01

    This book is a comprehensive compilation of earthquake- and tsunami-related technologies and knowledge for the design and construction of nuclear facilities. As such, it covers a wide range of fields including civil engineering, architecture, geotechnical engineering, mechanical engineering, and nuclear engineering, for the development of new technologies providing greater resistance against earthquakes and tsunamis. It is crucial both for students of nuclear energy courses and for young engineers in nuclear power generation industries to understand the basics and principles of earthquake- and tsunami-resistant design of nuclear facilities. In Part I, "Seismic Design of Nuclear Power Plants", the design of nuclear power plants to withstand earthquakes and tsunamis is explained, focusing on buildings, equipment's, and civil engineering structures. In Part II, "Basics of Earthquake Engineering", fundamental knowledge of earthquakes and tsunamis as well as the dynamic response of structures and foundation ground...

  8. Optimal control of hydroelectric facility incorporating pump storage

    International Nuclear Information System (INIS)

    Zhao, Guangzhi; Davison, Matt

    2009-01-01

    We consider a simple model of a pump-assisted hydroelectric facility operating in a market with time-varying but deterministic power prices and constant water inflows. The engineering details of the facility are described by a model containing several parameters. We present an algorithm for optimizing first the energy and then the profit produced by these plants. This algorithm allows us to describe the relationships between control trajectory and time, and between inflow and price. Remarkably, we see that under some reasonable choices of facility parameters and for power prices that are not extremely variable, the optimal profit operation of these facilities is not too different from their optimal energy operation, and the control is less affected by the price as the inflow rate increases. (author)

  9. Airborne & Field Sensors Facilities

    Data.gov (United States)

    Federal Laboratory Consortium — RTTC facilities include an 800' x 60' paved UAV operational area, clearapproach/departure zone, concrete pads furnished with 208VAC, 3 phase,200 amp power, 20,000 sq...

  10. 26 CFR 1.141-7 - Special rules for output facilities.

    Science.gov (United States)

    2010-04-01

    .... (b) Definitions. For purposes of this section and § 1.141-8, the following definitions and rules... legislature in State X to own and operate certain power generating facilities, sells all of the power from its... generation, transmission and distribution facilities. In 2003, D transfers operating control of its...

  11. Dry Well Storage Facility conceptual design study

    International Nuclear Information System (INIS)

    1979-02-01

    The Dry Well Storage Facility described is assumed to be located adjacent to or near a Spent Fuel Receiving and Packaging Facility and/or a Packaged Fuel Transfer Facility. Performance requirements, quality levels and codes and standards, schedule and methods of performance, special requirements, quality assurance program, and cost estimate are discussed. Appendices on major mechanical equipment and electric power requirements are included

  12. Dry Well Storage Facility conceptual design study

    Energy Technology Data Exchange (ETDEWEB)

    1979-02-01

    The Dry Well Storage Facility described is assumed to be located adjacent to or near a Spent Fuel Receiving and Packaging Facility and/or a Packaged Fuel Transfer Facility. Performance requirements, quality levels and codes and standards, schedule and methods of performance, special requirements, quality assurance program, and cost estimate are discussed. Appendices on major mechanical equipment and electric power requirements are included.

  13. FY 1998 evaluation/analysis by site of the data collected in the field test project for photovoltaic power generation for public facilities. 4/4; 1998 nendo kokyo shisetsu nadoyo taiyoko hatsuden field test jigyo ni okeru shushu data hyoka kaiseki kaku site betsu. 4/4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    The data items are horizontal insolation intensity, inclined insolation intensity, effective inclined insolation intensity (each unit: kWh/m{sup 2}), average temperature, array power energy, system power energy, system consumption power, load power energy, system supply load, and back flow power energy (each unit: kWh). Besides, the number of interconnected protective movement, disconnection hour (minute), system operating hour (minute), independent operating load, independent supply load (each unit: kWh), equivalent array operating hour, equivalent system operating hour, array/system output coefficient, system utilization rate/power generation rate, INV effective efficiency, and INV load factor. The objects of field tests are government office (joint office building, etc.), school (college, high school, elementary school, etc.), the Shinkansen Kyoto Station, health/welfare facilities (health facilities for the elderly, welfare center, etc.), hospital, industrial experimental station, training facilities (exhibition training facilities, etc.), broadcasting facilities, etc. (NEDO)

  14. The ORION Facility

    International Nuclear Information System (INIS)

    Noble, Robert

    2003-01-01

    ORION will be a user-oriented research facility for understanding the physics and developing the technology for future high-energy particle accelerators, as well as for research in related fields. The facility has as its centerpiece the Next Linear Collider Test Accelerator (NLCTA) at the Stanford Linear Accelerator Center (SLAC). The NLCTA will be modified with the addition of a new, high-brightness photoinjector, its drive laser, an S-band rf power system, a user laser room, a low-energy experimental hall supplied with electron beams up to 60 MeV in energy, and a high-energy hall supplied with beams up to 350 MeV. The facility design and parameters are described here along with highlights from the 2nd ORION Workshop held in February 2003

  15. Improvement of Oil-Vapor Treatment Facility for Wolsong Unit 3,4

    International Nuclear Information System (INIS)

    Kim, Jeong Guk; Kwon, S. W.; Lee, H. S.

    2009-11-01

    With the purpose to minimize an oil-vapor discharge to the atmosphere and to be an environmentally friendly nuclear power plant by an improvement of mist eliminator for turbine lubricant system at Wolsong Nuclear Power Plant Unit 3,4, this project - project name : Improvement of Oil-vapor Treatment Facility for Wolsong Unit 3,4 - was conducted for six months (from Apr. 15, 2009 to Oct. 14, 2009). This Project contains Oil-vapor Source and Environmental Regulation, Analysis on the Present Oil-vapor Treatment Facility, Improvement of Oil-vapor Treatment Facility, Test Facility Design, Fabrication, Installation, Test Operation, Evaluation of the Facility

  16. Gas cooled fast breeder reactor design for a circulator test facility (modified HTGR circulator test facility)

    Energy Technology Data Exchange (ETDEWEB)

    1979-10-01

    A GCFR helium circulator test facility sized for full design conditions is proposed for meeting the above requirements. The circulator will be mounted in a large vessel containing high pressure helium which will permit testing at the same power, speed, pressure, temperature and flow conditions intended in the demonstration plant. The electric drive motor for the circulator will obtain its power from an electric supply and distribution system in which electric power will be taken from a local utility. The conceptual design decribed in this report is the result of close interaction between the General Atomic Company (GA), designer of the GCFR, and The Ralph M. Parson Company, architect/engineer for the test facility. A realistic estimate of total project cost is presented, together with a schedule for design, procurement, construction, and inspection.

  17. Facility Description 2012. Summary report of the encapsulation plant and disposal facility designs

    International Nuclear Information System (INIS)

    Palomaeki, J.; Ristimaeki, L.

    2013-10-01

    The purpose of the facility description is to be a specific summary report of the scope of Posiva's nuclear facilities (encapsulation plant and disposal facility) in Olkiluoto. This facility description is based on the 2012 designs and completing Posiva working reports. The facility description depicts the nuclear facilities and their operation as the disposal of spent nuclear fuel starts in Olkiluoto in about 2020. According to the decisions-in-principle of the government, the spent nuclear fuel from Loviisa and Olkiluoto nuclear power plants in operation and in future cumulative spent nuclear fuel from Loviisa 1 and 2, Olkiluoto 1, 2, 3 and 4 nuclear power plants, is permitted to be disposed of in Olkiluoto bedrock. The design of the disposal facility is based on the KBS-3V concept (vertical disposal). Long-term safety concept is based on the multi-barrier principle i.e. several release barriers, which ensure one another so that insufficiency in the performance of one barrier doesn't jeopardize long-term safety of the disposal. The release barriers are the following: canister, bentonite buffer and deposition tunnel backfill, and the host rock around the repository. The canisters are installed into the deposition holes, which are bored to the floor of the deposition tunnels. The canisters are enveloped with compacted bentonite blocks, which swell after absorbing water. The surrounding bedrock and the central and access tunnel backfill provide additional retardation, retention, and dilution. The nuclear facilities consist of an encapsulation plant and of underground final disposal facility including other aboveground buildings and surface structures serving the facility. The access tunnel and ventilation shafts to the underground disposal facility and some auxiliary rooms are constructed as a part of ONKALO underground rock characterization facility during years 2004-2014. The construction works needed for the repository start after obtaining the construction

  18. Problems of development and putting into education process an electronic textbook on special discipline 'General theory and construction of heat-and-power engineering facilities'

    International Nuclear Information System (INIS)

    Karitskaya, S.G.; Ruzanov, K.A.; Davletov, V.S.

    2005-01-01

    The results of work of making the electronic textbook of special discipline ('General theory and construction of heat-and-power engineering facilities' are brought. The principles and requirements, presented towards literature of such type, are outlined. (author)

  19. Nuclear facilities in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    1991-01-01

    The information brochure is a survey of installed nuclear facilities in Germany, presenting on one page each a picture of a nuclear power plant together with the main relevant data, or of other type of nuclear facilities belonging to the nuclear fuel cycle (such as fuel production plant, fuel production plant, fuel element storage facilities, and facilities for spent fuel and waste management). (UA) [de

  20. Report on operation of nuclear facilities in Slovenia in 1991

    International Nuclear Information System (INIS)

    1992-11-01

    Slovenian Nuclear Safety Administration (SNSA) is responsible for: nuclear safety, transport of nuclear and radioactive materials, safeguarding nuclear materials, and conducting regulatory process related to liability for nuclear damage, qualification and training of operators at nuclear facilities, quality assurance and inspection of nuclear facilities. The major nuclear facility supervised by SNSA is the Nuclear Power Plant in Krsko with a pressurized water reactor of 632 MW electric power. Beside the nuclear power plant, TRIGA Mark 11 Research Reactor of 250 kW thermal power operates within the Reactor Center of Jozef Stefan Institute. There is an interim storage of low and medium radioactive waste at the Reactor Center. Also the Uranium mine Zirovski Vrh was supervised by SNSA. All the nuclear power facilities in Republic of Slovenia were operating safely in 1991. There were no significant events that could be evaluated as a safety problem or a breach of technical specifications. A great part of activities of SNSA was focused on the next visit of the IAEA OSART team (Operational Safety Assessment Review Team) in Krsko Nuclear Power Plant and on the visit of the INSARR mission (Integrated Safety Assessment of Research Reactors) for the TRIGA Mark 11 Research Reactor. (author)

  1. Thermal-hydraulic tests with out-of-pile test facility for BOCA development

    International Nuclear Information System (INIS)

    Kitagishi, Shigeru; Aoyama, Masashi; Tobita, Masahiro; Inaba, Yoshitomo; Yamaura, Takayuki

    2012-01-01

    The fuel transient test facility was prepared for power ramping tests of light-water-reactor (LWR) fuels in the Japan Materials Testing Reactor (JMTR) under a contract project with the Nuclear Industrial Safety Agent (NISA) of the Ministry of Economy, Trade and Industry (METI). It is necessary to develop high accuracy analysis procedure for power ramping tests after restart of the JMTR. The out-of-pile test facility to simulate thermal-hydraulic conditions of the fuel transient test facility was therefore developed. Applicability of the analysis code ACE-3D was examined for thermal-hydraulic analysis of power ramping tests for 10x10 BWR fuels by the fuel transient test facility. As the results, the calculated temperature was 304°C in comparison with measured value of 304.9-317.4°C in the condition of 600 W/cm. There is a bright prospect of high accuracy power ramping tests by the fuel transient test facility in JMTR. (author)

  2. Reactor Sharing at Rensselaer Critical Facility

    International Nuclear Information System (INIS)

    D. Steiner, D. Harris, T. Trumbull

    2006-01-01

    This final report summarizes the reactor sharing activities at the Rensselaer Critical Facility. An example of a typical tour is also included. Reactor sharing at the RCF brings outside groups into the facility for a tour, an explanation of reactor matters, and a reactor measurement. It has involved groups ranging from high school classes to advanced college groups and in size from a few to about 50 visitors. The RCF differs from other university reactors in that its fuel is like that of large power reactors, and its research and curriculum are dedicated to power reactor matters

  3. The concept of the double-purpose electro-nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Bergelson, B.P.; Balyuk, S.A. [Institute of theoretical and experimental physics, Moscow (Russian Federation)

    1995-10-01

    The parameters have been determined on a conceptual level of the electro-nuclear facility intended for electric power generation and minor actinide transmutation. Electro-nuclear facilities (ENFs) have been developed without apparent success for many years. The main difficulties are associated with high accelerator cost and absence of their own clearly defined place for ENFs in the nuclear-power complex. In recent years, however, the situation has changed in many aspects in connection with the rise in safety requirements for nuclear power industry and because of the necessity to decrease the equilibrium level of the long-lived radiotoxicity in particular. In the authors opinion double-purpose ENFs designed for power generation and tansmutation of minor actinides are promising. The results of conceptual investigations for such a facility being operated on liquid fuel in the condition of a uranium-plutonium fuel cycle are given here.

  4. Simulation based assembly and alignment process ability analysis for line replaceable units of the high power solid state laser facility

    International Nuclear Information System (INIS)

    Wang, Junfeng; Lu, Cong; Li, Shiqi

    2016-01-01

    Highlights: • Discrete event simulation is applied to analyze the assembly and alignment process ability of LRUs in SG-III facility. • The overall assembly and alignment process of LRUs with specific characteristics is described. • An extended-directed graph is proposed to express the assembly and alignment process of LRUs. • Different scenarios have been simulated to evaluate assembling process ability of LRUs and decision making is supported to ensure the construction millstone. - Abstract: Line replaceable units (LRUs) are important components of the very large high power solid state laser facilities. The assembly and alignment process ability of LRUs will impact the construction milestone of facilities. This paper describes the use of discrete event simulation method for assembly and alignment process analysis of LRUs in such facilities. The overall assembly and alignment process for LRUs is presented based on the layout of the optics assembly laboratory and the process characteristics are analyzed. An extended-directed graph is proposed to express the assembly and alignment process of LRUs. Taking the LRUs of disk amplifier system in Shen Guang-III (SG-III) facility as the example, some process simulation models are built based on the Quest simulation platform. The constraints, such as duration, equipment, technician and part supply, are considered in the simulation models. Different simulation scenarios have been carried out to evaluate the assembling process ability of LRUs. The simulation method can provide a valuable decision making and process optimization tool for the optics assembly laboratory layout and the process working out of such facilities.

  5. Simulation based assembly and alignment process ability analysis for line replaceable units of the high power solid state laser facility

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Junfeng; Lu, Cong; Li, Shiqi, E-mail: sqli@hust.edu.cn

    2016-11-15

    Highlights: • Discrete event simulation is applied to analyze the assembly and alignment process ability of LRUs in SG-III facility. • The overall assembly and alignment process of LRUs with specific characteristics is described. • An extended-directed graph is proposed to express the assembly and alignment process of LRUs. • Different scenarios have been simulated to evaluate assembling process ability of LRUs and decision making is supported to ensure the construction millstone. - Abstract: Line replaceable units (LRUs) are important components of the very large high power solid state laser facilities. The assembly and alignment process ability of LRUs will impact the construction milestone of facilities. This paper describes the use of discrete event simulation method for assembly and alignment process analysis of LRUs in such facilities. The overall assembly and alignment process for LRUs is presented based on the layout of the optics assembly laboratory and the process characteristics are analyzed. An extended-directed graph is proposed to express the assembly and alignment process of LRUs. Taking the LRUs of disk amplifier system in Shen Guang-III (SG-III) facility as the example, some process simulation models are built based on the Quest simulation platform. The constraints, such as duration, equipment, technician and part supply, are considered in the simulation models. Different simulation scenarios have been carried out to evaluate the assembling process ability of LRUs. The simulation method can provide a valuable decision making and process optimization tool for the optics assembly laboratory layout and the process working out of such facilities.

  6. EXPERIENCE AND PLANS OF THE JLAB FEL FACILITY AS A USER FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Michelle D. Shinn

    2007-08-26

    Jefferson Lab's IR Upgrade FEL building was planned from the beginning to be a user facility, and includes an associated 600 m2 area containing seven laboratories. The high average power capability (multikilowatt-level) in the near-infrared (1-3 microns), and many hundreds of watts at longer wavelengths, along with an ultrafast (~ 1 ps) high PRF (10's MHz) temporal structure makes this laser a unique source for both applied and basic research. In addition to the FEL, we have a dedicated laboratory capable of delivering high power (many tens of watts) of broadband THz light. After commissioning the IR Upgrade, we once again began delivering beam to users in 2005. In this presentation, I will give an overview of the FEL facility and its current performance, lessons learned over the last two years, and a synopsis of current and future experiments.

  7. Catalogue and classification of technical safety standards, rules and regulations for nuclear power reactors and nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Fichtner, N.; Becker, K.; Bashir, M.

    1977-01-01

    The present report is an up-dated version of the report 'Catalogue and Classification of Technical Safety Rules for Light-water Reactors and Reprocessing Plants' edited under code No EUR 5362e, August 1975. Like the first version of the report, it constitutes a catalogue and classification of standards, rules and regulations on land-based nuclear power reactors and fuel cycle facilities. The reasons for the classification system used are given and discussed

  8. United States Advanced Ultra-Supercritical Component Test Facility for 760°C Steam Power Plants ComTest Project

    Energy Technology Data Exchange (ETDEWEB)

    Hack, Horst [Electric Power Research Institute (EPRI); Purgert, Robert Michael [Energy Industries of Ohio

    2017-12-13

    Following the successful completion of a 15-year effort to develop and test materials that would allow coal-fired power plants to be operated at advanced ultra-supercritical (A-USC) steam conditions, a United States-based consortium is presently engaged in a project to build an A-USC component test facility (ComTest). A-USC steam cycles have the potential to improve cycle efficiency, reduce fuel costs, and reduce greenhouse gas emissions. Current development and demonstration efforts are focused on enabling the construction of A-USC plants, operating with steam temperatures as high as 1400°F (760°C) and steam pressures up to 5000 psi (35 MPa), which can potentially increase cycle efficiencies to 47% HHV (higher heating value), or approximately 50% LHV (lower heating value), and reduce CO2 emissions by roughly 25%, compared to today’s U.S. fleet. A-USC technology provides a lower-cost method to reduce CO2 emissions, compared to CO2 capture technologies, while retaining a viable coal option for owners of coal generation assets. Among the goals of the ComTest facility are to validate that components made from advanced nickel-based alloys can operate and perform under A-USC conditions, to accelerate the development of a U.S.-based supply chain for the full complement of A-USC components, and to decrease the uncertainty of cost estimates for future A-USC power plants. The configuration of the ComTest facility would include the key A-USC technology components that were identified for expanded operational testing, including a gas-fired superheater, high-temperature steam piping, steam turbine valve, and cycling header component. Membrane walls in the superheater have been designed to operate at the full temperatures expected in a commercial A-USC boiler, but at a lower (intermediate) operating pressure. This superheater has been designed to increase the temperature of the steam supplied by the host utility boiler up to 1400°F (760

  9. Trend chart: wind power. Third quarter 2015

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2015-11-01

    This publication presents the wind energy situation of continental France and overseas territories during the third quarter 2015: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, methodology used

  10. Trend chart: wind power. Forth quarter 2016

    International Nuclear Information System (INIS)

    Coltier, Yves

    2017-02-01

    This publication presents the wind energy situation of continental France and overseas territories during the forth quarter 2016: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, methodology used

  11. Trend chart: wind power. First quarter 2016

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2016-05-01

    This publication presents the wind energy situation of continental France and overseas territories during the first quarter 2016: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, methodology used

  12. Trend chart: wind power. Third quarter 2016

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2016-11-01

    This publication presents the wind energy situation of continental France and overseas territories during the third quarter 2016: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, methodology used

  13. Trend chart: wind power. Second quarter 2016

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2016-08-01

    This publication presents the wind energy situation of continental France and overseas territories during the second quarter 2016: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, methodology used

  14. Trend chart: wind power. First quarter 2017

    International Nuclear Information System (INIS)

    2017-05-01

    This publication presents the wind energy situation of continental France and overseas territories during the first quarter 2017: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, methodology used

  15. Trend chart: wind power. Forth quarter 2015

    International Nuclear Information System (INIS)

    Reynaud, Didier

    2016-02-01

    This publication presents the wind energy situation of continental France and overseas territories during the forth quarter 2015: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, methodology used

  16. Conceptual design study advanced concepts test (ACT) facility

    Energy Technology Data Exchange (ETDEWEB)

    Zaloudek, F.R.

    1978-09-01

    The Advanced Concepts Test (ACT) Project is part of program for developing improved power plant dry cooling systems in which ammonia is used as a heat transfer fluid between the power plant and the heat rejection tower. The test facility will be designed to condense 60,000 lb/hr of exhaust steam from the No. 1 turbine in the Kern Power Plant at Bakersfield, CA, transport the heat of condensation from the condenser to the cooling tower by an ammonia phase-change heat transport system, and dissipate this heat to the environs by a dry/wet deluge tower. The design and construction of the test facility will be the responsibility of the Electric Power Research Institute. The DOE, UCC/Linde, and the Pacific Northwest Laboratories will be involved in other phases of the project. The planned test facilities, its structures, mechanical and electrical equipment, control systems, codes and standards, decommissioning requirements, safety and environmental aspects, and energy impact are described. Six appendices of related information are included. (LCL)

  17. Transmission cost minimization strategies for wind-electric generating facilities

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez, R. [Northern States Power Company, Minneapolis, MN (United States)

    1997-12-31

    Integrating wind-electric generation facilities into existing power systems presents opportunities not encountered in conventional energy projects. Minimizing outlet cost requires probabilistic value-based analyses appropriately reflecting the wind facility`s operational characteristics. The wind resource`s intermittent nature permits relaxation of deterministic criteria addressing outlet configuration and capacity required relative to facility rating. Equivalent capacity ratings of wind generation facilities being a fraction of installed nameplate rating, outlet design studies contingency analyses can concentrate on this fractional value. Further, given its non-dispatchable, low capacity factor nature, a lower level of redundancy in outlet facilities is appropriate considering the trifling contribution to output unreliability. Further cost reduction opportunities arise from {open_quotes}wind speed/generator power output{close_quotes} and {open_quotes}wind speed/overhead conductor rating{close_quotes} functions` correlation. Proper analysis permits the correlation`s exploitation to safely increase line ratings. Lastly, poor correlation between output and utility load may permit use of smaller conductors, whose higher (mostly off-peak) losses are economically justifiable.

  18. Trend chart: wind power. Second quarter 2017

    International Nuclear Information System (INIS)

    2017-08-01

    This publication presents the wind energy situation of continental France and overseas territories during the second quarter 2017: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, revision of results

  19. Trend chart: wind power. Fourth quarter 2017

    International Nuclear Information System (INIS)

    Moreau, Sylvain

    2018-02-01

    This publication presents the wind energy situation of continental France and overseas territories during the fourth quarter 2017: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, revision of results

  20. Trend chart: wind power. Third quarter 2017

    International Nuclear Information System (INIS)

    2017-11-01

    This publication presents the wind energy situation of continental France and overseas territories during the third quarter 2017: total connected load, new connected facilities, regional distribution of wind power production, evolution of quarterly production, distribution of facilities versus power, evolution forecasts of the French wind power park, projects in progress, detailed regional results, revision of results

  1. The Texts of the Instruments Concerning the Agency's assistance to Mexico in Establishing a Nuclear Power Facility. A Second Supply Agreement

    International Nuclear Information System (INIS)

    1974-01-01

    As a sequel to the assistance which the Agency provided to the Government of Mexico in establishing a nuclear power facility, a Second Supply Agreement has been concluded between the Agency and that Government. The Agreement entered into force on 14 June 1974, pursuant to Article IX, and the text thereof is reproduced herein for the information of all Members.

  2. The Texts of the Instruments Concerning the Agency's assistance to Mexico in Establishing a Nuclear Power Facility. A Second Supply Agreement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1974-10-31

    As a sequel to the assistance which the Agency provided to the Government of Mexico in establishing a nuclear power facility, a Second Supply Agreement has been concluded between the Agency and that Government. The Agreement entered into force on 14 June 1974, pursuant to Article IX, and the text thereof is reproduced herein for the information of all Members.

  3. Managing public acceptance for a new enrichment facility

    International Nuclear Information System (INIS)

    Boyd, M.

    1992-01-01

    The Claiborne Enrichment Center has many first associated with it, and a solid nuclear-based community relations experience has been combined with fly-by-the-seat-of-your-pants techniques to successfully introduce a first-of-a-kind facility not only to Louisiana, but also to the US. The project is being developed by Louisiana Energy Services (LES), a limited partnership consisting of Urenco, the European enrichment consortium that operates centrifuge enrichment facilities in the United Kingdom, the Netherlands, and Germany; Fluor Daniel, an internationally known engineering and construction firm; and three utilities - Duke Power, Northern States Power, and Louisiana Power and Light (LP and L). Louisiana Energy will build the nation's first privately owned uranium enrichment facility. It will be the first commercial use of centrifuge technology for enrichment in the US. Some of the community relations challenges the project has had and their solutions are described

  4. HANJUNG`s overseas marketing for power industry

    Energy Technology Data Exchange (ETDEWEB)

    Cho, B.K. [Korea Heavy Industries and Construction Co., Ltd., Hanjung (Korea, Democratic People`s Republic of)

    1994-12-31

    The Korean government has a strong policy for developing local industries for producing power plant facilities. Korea Heavy Industries and Construction Co. Ltd. (HANJUNG) is a prime contractor for the design, construction, and installation of power plant facilities. The following topics are discussed: history of the electric power in Korea, the fabrication and supply of power plants in Korea, changing factors of the power plant business around the world, HANJUNG`s overseas marketing strategy, and Korea-US cooperation in third world countries.

  5. Construction and commissioning test report of the CEDM test facility

    Energy Technology Data Exchange (ETDEWEB)

    Chung, C. H.; Kim, J. T.; Park, W. M.; Youn, Y. J.; Jun, H. G.; Choi, N. H.; Park, J. K.; Song, C. H.; Lee, S. H.; Park, J. K

    2001-02-01

    The test facility for performance verification of the control element drive mechanism (CEDM) of next generation power plant was installed at the site of KAERI. The CEDM was featured a mechanism consisting of complicated mechanical parts and electromagnetic control system. Thus, a new CEDM design should go through performance verification tests prior to it's application in a reactor. The test facility can simulate the reactor operating conditions such as temperature, pressure and water quality and is equipped with a test chamber to accomodate a CEDM as installed in the power plant. This test facility can be used for the following tests; endurance test, coil cooling test, power measurement and reactivity rod drop test. The commissioning tests for the test facility were performed up to the CEDM test conditions of 320 C and 150 bar, and required water chemistry was obtained by operating the on-line water treatment system.

  6. Construction and commissioning test report of the CEDM test facility

    International Nuclear Information System (INIS)

    Chung, C. H.; Kim, J. T.; Park, W. M.; Youn, Y. J.; Jun, H. G.; Choi, N. H.; Park, J. K.; Song, C. H.; Lee, S. H.; Park, J. K.

    2001-02-01

    The test facility for performance verification of the control element drive mechanism (CEDM) of next generation power plant was installed at the site of KAERI. The CEDM was featured a mechanism consisting of complicated mechanical parts and electromagnetic control system. Thus, a new CEDM design should go through performance verification tests prior to it's application in a reactor. The test facility can simulate the reactor operating conditions such as temperature, pressure and water quality and is equipped with a test chamber to accomodate a CEDM as installed in the power plant. This test facility can be used for the following tests; endurance test, coil cooling test, power measurement and reactivity rod drop test. The commissioning tests for the test facility were performed up to the CEDM test conditions of 320 C and 150 bar, and required water chemistry was obtained by operating the on-line water treatment system

  7. Remote maintenance system for nuclear facilities

    International Nuclear Information System (INIS)

    Maeda, Masafumi

    1993-01-01

    In the facilities related to atomic energy, from the viewpoint of the reduction of radiation exposure of workers and the heightening of the rate of operation of the facilities, the development of remote maintenance system is regarded as important. Meidensha Electric Manufacturing Co., Ltd. developed the bilateral control type manipulator, BILARM-83, in 1979, and has developed high performance manipulator systems. As the design of the plant that realizes the remote operation maintenance of process machinery and equipment during plant operation, the remote maintenance system by canyon cell techniques, which was adopted in Savannah River plant, USA, and has been operated for nearly 50 years, has been known. The concept of the full remote maintenance system by large scale cell techniques was shown and has been developed by Power Reactor and Nuclear Fuel Development Corp. In order to realize the remote maintenance of such large scale cells, Meidensha is developing the both arm type bilateral servo manipulator, the single arm type power manipulator, the transport system for moving them, the power and signal system and so on. Those systems were adopted for the glass solidification facilities. (K.I.)

  8. Community attitudes toward a proposed nuclear power generating facility as a function of expected outcomes

    International Nuclear Information System (INIS)

    Sundstrom, E.; Lounsbury, J.W.; Schuller, C.R.; Fowler, J.R.; Mattingly, T.J. Jr.

    1977-01-01

    The relationship between attitudes toward a proposed nuclear power generating facility and the outcomes expected to accompany it are examined. In a survey of 350 residents of a small rural community, approximately 2/3 expressed favorable attitudes toward the proposed nuclear plant. A principal components factor analysis of the anticipated likelihoods of outcomes of the plant revealed five factors: hazards, economic growth, lower costs, social disruption, and community visibility. Using these factors as predictors, a simple multiple regression equation accounted for 52% of the variation in attitudes toward the plant. The strongest predictor was the perceived likelihood of hazards. These findings are discussed in terms of the relationship between attitudes and expectations, and in relation to decisions regarding public policy

  9. 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)

  10. Blowdown mass flow measurements during the Power Burst Facility LOC-11C test

    International Nuclear Information System (INIS)

    Broughton, J.M.; MacDonald, P.E.

    1979-01-01

    An interpretation and evaluation of the two-phase coolant mass flow measurements obtained during Test LOC-11C performed in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory (INEL) are presented. Although a density gradient existed within the pipe between 1 and 6 s, the homogeneous flow model used to calculate the coolant mass flow from the measured mixture density, momentum flux, and volumetric flow was found to be generally satisfactory. A cross-sectional average density was determined by fitting a linear density gradient through the upper and lower chordal densities obtained from a three-beam gamma densitometer and then combining the result with the middle beam density. The integrated measured coolant mass flow was subsequently found to be within 5% if the initial mass inventory of the PBF loss-of-coolant accident (LOCA) system. The posttest calculations using the RELAP4/MOD6 computer code to determine coolant mass flow for Test LOC-11C also agreed well with the measured data

  11. Green power programs in Canada : 2003 : overview of Government green power policies, utility green power implementation initiatives, green power and certificate marketing programs, and their benefits

    International Nuclear Information System (INIS)

    Whitmore, J.; Bramley, M.; Holmes, R.

    2004-09-01

    Green power is defined as electricity produced from renewable sources, and whose production has low adverse impacts on the environment, human health and communities. Green power has near-zero greenhouse gas (GHG) emissions and includes sources such as wind, hydro, and solar power. It offers several environmental benefits, as well as the enhancement of energy security, regional development, economic diversification and the creation of skilled jobs. There are four categories of programs related to green power development in Canada: government green power policies, utility green power development programs, green power marketing initiatives, and green power certificate marketing initiatives. Most of the activities in Canada associated with these four categories in 2003 were discussed in this report. However, difficulties with quantification prevented the inclusion of some green power activities such as (1) the generation of green power not certified or identified by the generator as green power, (2) industry or residential self-generation, (3) net metering, and (4) small government programs. Green power generation facilities in 2003 totaled 775 MW of capacity compared to 539 MW in 2002. Hydro capacity represented 41 per cent, followed by wind capacity at 40 per cent and wood waste at 17 per cent. Most of the green power generation facilities in 2003 were located in Alberta, followed by British Columbia, Ontario and Quebec. 230 refs., 8 tabs., 1 fig

  12. Sea water pumping-up power plant system combined with nuclear power plant

    International Nuclear Information System (INIS)

    Ichiki, Tadaharu; Tanaka, Masayuki.

    1991-01-01

    It is difficult to find a site suitable to construction for a sea water pumping-up power plant at a place relatively near the electric power consumption area. Then, a nuclear power plant is set at the sea bottom or the land portion of a sea shore near the power consumption area. A cavity is excavated underground or at the bottom of the sea in the vicinity of the power plant to form a lower pond, and the bottom of the sea, as an upper pond and the lower pond are connected by a water pressure pipe and a water discharge pipe. A pump water turbine is disposed therebetween, to which electric power generator is connected. In addition, an ordinary or emergency cooling facility in the nuclear power plant is constituted such that sea water in the cavity is supplied by a sea water pump. Accordingly, the sea water pumping-up plant system in combination with the nuclear power plant is constituted with no injuring from salts to animals and plants on land in the suburbs of a large city. The cost for facilities for supplying power from a remote power plant to large city areas and power loss are decreased and stable electric power can be supplied. (N.H.)

  13. Annual report to the Laser Facility Committee 1984

    International Nuclear Information System (INIS)

    1984-01-01

    The report describes the work carried out at, or in association with, the Central Laser Facility (CLF), during the year ending March 1984. The CLF programme is divided into three main sections. The first, the glass laser scientific programme, is concerned with applications of the high power Nd glass laser. The second, the ultra violet radiation facility scientific programme, involves the excimer pumped frequency tunable lasers. The last, high power KrF laser development, describes Research and development work on this laser. (U.K.)

  14. Development of thermo-plastic heating and compaction facility

    International Nuclear Information System (INIS)

    Ko, Dae Hak; Lim, Suk Nam

    1998-01-01

    Low- and intermediate-level radioactive wastes consist of spent resin, spent filter, concentrated waste and dry active waste(DAW) and they are solidified or packaged into drums or high integrated containers(HICs). DAWs occupy 50 percent of all low- and intermediate-level radioactive wastes generated from nuclear power plants in Korea. Incinerable wastes in the DAWs are about 60 percent. Therefore, it is very important for us to reduce the volume of incinerable wastes in DAWs. Experience of supercompaction turned out that thermo-plastic wastes have a swelling effect after supercompaction process due to their repulsive power. And the thermo-plastic heating and compaction facility has been developed by KEPCO. In conclusion, heating and compaction facility can reduce the volume of DAWs as well as upgrade the quality of treated wastes, because the swelling effect by repulsive power after compaction is removed, final wastes form the shape of block and they have no free-standing water in the wastes. Plan for practical use is that this facility will be installed in other nuclear power plants in Korea in 1999. (Cho, G. S.). 1 tab., 2 figs

  15. 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

  16. Operational Radiation Protection in Synchrotron Light and Free Electron Laser Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Liu, James C.; Rokni, Sayed H.; /SLAC; Vylet, Vaclav; /Jefferson Lab

    2009-12-11

    The 3rd generation synchrotron radiation (SR) facilities are storage ring based facilities with many insertion devices and photon beamlines, and have low injection beam power (< few tens of watts), but extremely high stored beam power ({approx} 1 GW). The 4th generation x-ray free electron laser (FEL) facilities are based on an electron Linac with a long undulator and have high injection beam power (a few kW). Due to its electron and photon beam characteristics and modes of operation, storage ring and photon beamlines have unique safety aspects, which are the main subjects of this paper. The shielding design limits, operational modes, and beam losses are first reviewed. Shielding analysis (source terms and methodologies) and interlocked safety systems for storage ring and photon beamlines (including SR and gas bremsstrahlung) are described. Specific safety issues for storage ring top-off injection operation and FEL facilities are discussed. The operational safety program, e.g., operation authorization, commissioning, training, and radiation measurements, for SR facilities is also presented.

  17. Operational Radiation Protection in Synchrotron Light and Free Electron Laser Facilities

    International Nuclear Information System (INIS)

    Liu, James C.; Rokni, Sayed H.; Vylet, Vaclav

    2009-01-01

    The 3rd generation synchrotron radiation (SR) facilities are storage ring based facilities with many insertion devices and photon beamlines, and have low injection beam power (< few tens of watts), but extremely high stored beam power (∼ 1 GW). The 4th generation x-ray free electron laser (FEL) facilities are based on an electron Linac with a long undulator and have high injection beam power (a few kW). Due to its electron and photon beam characteristics and modes of operation, storage ring and photon beamlines have unique safety aspects, which are the main subjects of this paper. The shielding design limits, operational modes, and beam losses are first reviewed. Shielding analysis (source terms and methodologies) and interlocked safety systems for storage ring and photon beamlines (including SR and gas bremsstrahlung) are described. Specific safety issues for storage ring top-off injection operation and FEL facilities are discussed. The operational safety program, e.g., operation authorization, commissioning, training, and radiation measurements, for SR facilities is also presented.

  18. Power supply for nuclear power plant home consumption using inverter sources

    International Nuclear Information System (INIS)

    Stepar, V.; Tvrdik, J.

    1988-01-01

    A description is presented of the system configuration of a nuclear power plant with WWER-440 and WWER-1000 units and of a system of guaranteed power supply for the plant home consumption network for a WWER-440 power plant. The power supply network consists of 6 inverter supplies for safety systems, 4 supplies for nonsystem facilities and of a minimum of three power supplies for facilities outside the units. A diagram is shown and the principle described of the currently used ABP 1500 power supply system of Soviet origin. Using the experience from its operation, a Czechoslovak inverter supply system was designed featuring parallel operation of the inverter units. The principles are given for the design of a power supply system of an output of 75 kVA, the diagram is shown and the principle described. The design allows implementing and using the system without redundancy or in redundant operation of the 2 from 3 type at an installed capacity of 66%, or of the 1 from 2 type at an installed capacity of 50% of the output. The system is undergoing tests that should verify its reliability. (J.B.). 3 figs., 1 tab

  19. Operational status of nuclear facilities in Japan. 2012 edition

    International Nuclear Information System (INIS)

    2012-01-01

    This document is a compilation which provides an outline of the administration of nuclear facility safety regulations as well as various data including operational status, the status of periodical and safety inspections, the status of issues, and radiation management on nuclear power reactor facilities, reactor facilities in the research and development stage, and fabrication, reprocessing, disposal, and storage facilities in fiscal year 2011 (from April 2011 to March 2012). (J.P.N.)

  20. Facility effluent monitoring plan for the 284-E and 284-W power plants

    International Nuclear Information System (INIS)

    Nickels, J.M.; Herman, D.R.

    1992-11-01

    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. A facility effluent monitoring plan determination was performed during calendar year 1991 and the evaluation requires the need for a facility effluent monitoring plan. 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

  1. Development of the ultra high efficiency thermal power generation facility

    Energy Technology Data Exchange (ETDEWEB)

    Sano, Toshihiro

    2010-09-15

    In order to prevent global warming, attention is focused on nuclear power generation and renewable energy such as wind and solar power generation. The electric power suppliers of Japan are aiming to increase the amount of nuclear and non-fossil fuel power generation over 50% of the total power generation by 2020. But this means that the remaining half will still be of thermal power generation using fossil fuel and will still play an important role. Under such circumstances, further efficiency improvement of the thermal power generation and its aggressive implementation is ongoing in Japan.

  2. Italian steam power plants

    Energy Technology Data Exchange (ETDEWEB)

    von Rautenkranz, J

    1939-01-01

    A brief history of geothermal power production in Italy is presented. Boric acid has been produced on an industrial scale since 1818. The first electrical power was generated in 1904, and by 1939 the output of geothermal power plants had reached 500 GWh, with major expansion of facilities planned.

  3. UGCT: New X-ray radiography and tomography facility

    International Nuclear Information System (INIS)

    Masschaele, B.C.; Cnudde, V.; Dierick, M.; Jacobs, P.; Hoorebeke, L. van; Vlassenbroeck, J.

    2007-01-01

    The UGCT (University Gent Computer Tomography) facility, a cooperation between the Radiation Physics research group and the Sedimentary Geology and Engineering Geology research group is a new CT facility providing a large range of scanning possibilities. Formerly a Skyscan 1072 was used to perform X-ray micro-CT scans at the UGCT facility and although this is a very powerful instrument, there were needs for a higher resolution and more flexibility. Therefore, the UCGT facility started the construction of a multidisciplinary micro-CT scanner inside a shielded room with a maximum flexibility of the set-up. The X-ray tube of this high-resolution CT scanner is a state-of-the-art open-type device with dual head: one head for high power micro-CT and one for sub-micro- or also called nano-CT. An important advantage of this scanner is that different detectors can be used to optimize the scanning conditions of the objects under investigation. The entire set-up is built on a large optical table to obtain the highest possible stability. Due to the flexible set-up and the powerful CT reconstruction software 'Octopus', it is possible to obtain the highest quality and the best signal-to-noise of the reconstructed images for each type of sample

  4. UGCT: New X-ray radiography and tomography facility

    Energy Technology Data Exchange (ETDEWEB)

    Masschaele, B.C. [Department of Subatomic and Radiation Physics, Ghent University, Proeftuinstraat 86, B-9000 Gent (Belgium)], E-mail: bert.masschaele@ugent.be; Cnudde, V. [Department of Geology and Soil Science, Ghent University, Krijgslaan 281, B-9000 Gent (Belgium); Dierick, M. [Department of Subatomic and Radiation Physics, Ghent University, Proeftuinstraat 86, B-9000 Gent (Belgium); Jacobs, P. [Department of Geology and Soil Science, Ghent University, Krijgslaan 281, B-9000 Gent (Belgium); Hoorebeke, L. van; Vlassenbroeck, J. [Department of Subatomic and Radiation Physics, Ghent University, Proeftuinstraat 86, B-9000 Gent (Belgium)

    2007-09-21

    The UGCT (University Gent Computer Tomography) facility, a cooperation between the Radiation Physics research group and the Sedimentary Geology and Engineering Geology research group is a new CT facility providing a large range of scanning possibilities. Formerly a Skyscan 1072 was used to perform X-ray micro-CT scans at the UGCT facility and although this is a very powerful instrument, there were needs for a higher resolution and more flexibility. Therefore, the UCGT facility started the construction of a multidisciplinary micro-CT scanner inside a shielded room with a maximum flexibility of the set-up. The X-ray tube of this high-resolution CT scanner is a state-of-the-art open-type device with dual head: one head for high power micro-CT and one for sub-micro- or also called nano-CT. An important advantage of this scanner is that different detectors can be used to optimize the scanning conditions of the objects under investigation. The entire set-up is built on a large optical table to obtain the highest possible stability. Due to the flexible set-up and the powerful CT reconstruction software 'Octopus', it is possible to obtain the highest quality and the best signal-to-noise of the reconstructed images for each type of sample.

  5. Material science experiments on the Atlas Facility

    International Nuclear Information System (INIS)

    Keinigs, Rhonald K.; Atchison, Walter L.; Faehl, Rickey J.; Lindemuth, Irvin R.; Anderson, Wallace E.; Bartsch, Robert Richard; Flower-Maudlin, Elane C.; Hammerberg, James E.; Holtkamp, David B.; Jones, Michael E.; Kyrala, George A.; Oro, David M.; Parker, Jerald V.; Preston, Dean L.; Reinovsky, Robert E.; Scudder, David W.; Sheehey, Peter T.; Shlacter, Jack S.; Stokes, John L.; Taylor, Antoinette J.; Tonks, Davis L.; Turchi, Peter J.

    2001-01-01

    Three material properties experiments that are to be performed on the Atlas pulsed power facility are described; friction at sliding metal interfaces, spallation and damage in convergent geomety, and plastic flow at high strain and high strain rate. Construction of this facility has been completed and experiments in high energy density hydrodynamics and material dynamics will begin in 2001.

  6. Oak Ridge rf Test Facility

    International Nuclear Information System (INIS)

    Gardner, W.L.; Hoffman, D.J.; McCurdy, H.C.; McManamy, T.J.; Moeller, J.A.; Ryan, P.M.

    1985-01-01

    The rf Test Facility (RFTF) of Oak Ridge National Laboratory (ORNL) provides a national facility for the testing and evaluation of steady-state, high-power (approx.1.0-MW) ion cyclotron resonance heating (ICRH) systems and components. The facility consists of a vacuum vessel and two fully tested superconducting development magnets from the ELMO Bumpy Torus Proof-of-Principle (EBT-P) program. These are arranged as a simple mirror with a mirror ratio of 4.8. The axial centerline distance between magnet throat centers is 112 cm. The vacuum vessel cavity has a large port (74 by 163 cm) and a test volume adequate for testing prototypic launchers for Doublet III-D (DIII-D), Tore Supra, and the Tokamak Fusion Test Reactor (TFTR). Attached to the internal vessel walls are water-cooled panels for removing the injected rf power. The magnets are capable of generating a steady-state field of approx.3 T on axis in the magnet throats. Steady-state plasmas are generated in the facility by cyclotron resonance breakdown using a dedicated 200-kW, 28-GHz gyrotron. Available rf sources cover a frequency range of 2 to 200 MHz at 1.5 kW and 3 to 18 MHz at 200 kW, with several sources at intermediate parameters. Available in July 1986 will be a >1.0-MW, cw source spanning 40 to 80 MHz. 5 figs

  7. Comparison of the cladding deformation measured during the Power Burst Facility loss-of-coolant accident in-pile experiments with recent Oak Ridge National Laboratory out-of-pile results

    International Nuclear Information System (INIS)

    Broughton, J.M.; McCardell, R.K.; MacDonald, P.E.

    1981-01-01

    A series of four large break loss-of-coolant accident fuel behavior experiments have been performed in the Power Burst Facility. The results of these experiments are briefly reviewed and compared with results from the ORNL multirod burst test program. The effect of cladding burst temperature and prior irradiation were investigated. The cladding strain of the previously irradiated test rods was more uniformly distributed around the cladding circumference and larger than for similar unirradiated test rods. The ORNL out-of-pile single rod test results are in good agreement with the Power Burst Facility (PBF) test results with unirradiated test rods, and the ORNL out-of-pile, single-rod test results with heated shrouds and the PBF test results with previously irradiated test rods are comparable

  8. Seismic reevaluation of nuclear facilities worldwide: Overview and status

    Energy Technology Data Exchange (ETDEWEB)

    Campbell, R D; Hardy, G S; Ravindra, M K [EQE International, Irvine, CA (United States); Johnson, J J [EQE International, San Francisco, CA (United States); Hoy, A J [EQE International Ltd., Birchwood, Warrington (United Kingdom)

    1995-07-01

    Existing nuclear facilities throughout the world are being subjected to severe scrutiny of their safety in tile event of an earthquake. In the United States, there have been several licensing and safety review issues for which industry and regulatory agencies have cooperated to develop rational and economically feasible criteria for resolving the issues. Currently, all operating nuclear power plants in the United States are conducting an Individual Plant Examination of External Events, including earthquakes beyond tile design basis. About two-thirds of tile operating plants are conducting parallel programs for verifying, tile seismic adequacy of equipment for the design basis earthquake. The U.S. Department of Energy is also beginning to perform detailed evaluations of their facilities, many of which had little or no seismic design. Western European countries also have been reevaluating their older nuclear power plants for seismic events often adapting the criteria developed in the United States. With the change in tile political systems in Eastern Europe, there is a strong emphasis from their Western European neighbors to evaluate and Upgrade tile safely of their operating nuclear power plants. Finally, nuclear facilities in Asia are, also, being evaluated for seismic vulnerabilities. This paper focuses oil tile methodologies that have been developed for reevaluation of existing nuclear power plants and presents examples of the application of these methodologies to nuclear facilities worldwide. (author)

  9. Seismic reevaluation of nuclear facilities worldwide: Overview and status

    International Nuclear Information System (INIS)

    Campbell, R.D.; Hardy, G.S.; Ravindra, M.K.; Johnson, J.J.; Hoy, A.J.

    1995-01-01

    Existing nuclear facilities throughout the world are being subjected to severe scrutiny of their safety in tile event of an earthquake. In the United States, there have been several licensing and safety review issues for which industry and regulatory agencies have cooperated to develop rational and economically feasible criteria for resolving the issues. Currently, all operating nuclear power plants in the United States are conducting an Individual Plant Examination of External Events, including earthquakes beyond tile design basis. About two-thirds of tile operating plants are conducting parallel programs for verifying, tile seismic adequacy of equipment for the design basis earthquake. The U.S. Department of Energy is also beginning to perform detailed evaluations of their facilities, many of which had little or no seismic design. Western European countries also have been reevaluating their older nuclear power plants for seismic events often adapting the criteria developed in the United States. With the change in tile political systems in Eastern Europe, there is a strong emphasis from their Western European neighbors to evaluate and Upgrade tile safely of their operating nuclear power plants. Finally, nuclear facilities in Asia are, also, being evaluated for seismic vulnerabilities. This paper focuses oil tile methodologies that have been developed for reevaluation of existing nuclear power plants and presents examples of the application of these methodologies to nuclear facilities worldwide. (author)

  10. Proposal for a verification facility of ADS in China

    International Nuclear Information System (INIS)

    Guan Xialing; Luo Zhanglin

    1999-01-01

    The concept, general layout and some specifications of a proposed verification facility of the accelerator driven radioactive clean nuclear power system (AD-RCNPS) in China are described. It is composed of a 150 MeV/3 mA low energy accelerator, a swimming pool reactor and some basic research facilities. The 150 MeV accelerator consists of an ECR proton source, LEBT, RFQ, CCDTL and SCC. As the sub-critical reactor, the swimming pool reactor is an existing research reactor at the China Institute of Atomic Energy, whose maximum output power is 3.5 MW. The effect of the instability of proton beam and possibility of simulation tests on the verification facility have been analysed. (author)

  11. Present status and forecast of T ampersand D facilities

    International Nuclear Information System (INIS)

    Ko, In-Suk.

    1994-01-01

    Before the end of the 1970s, because of our marvelous economic growth and industrial development we had made our best efforts to develop more power sources. But from the 1980s, KEPCO has invested for T ampersand D facility of high quality and improved system reliability. The main considerations for T ampersand D expansion are positive investment to improve facilities of the electric company, improvement of the quality of electrical equipment during manufacturing, and bettering the field construction of power facilities. In order to achieve the ultimate goal of supplying high quality electricity, we will try to improve cooperation between our domestic industries, and research institutes, and increase the exchange of international technology

  12. Proposal for a verification facility of ADS in China

    International Nuclear Information System (INIS)

    Guan Xialing; Luo Zhanglin

    2000-01-01

    The concept, the general layout and some specifications of a proposed verification facility of the accelerator driven radioactive clean nuclear power system (AD-RCNPS) in China has been described. It is composed of a 150 MeV/3 mA low energy accelerator, a swimming pool reactor and some basic research facility. The 150 MeV accelerator consists of an ECR proton source, LEBT, RFQ, CCDTL and SCC. As the sub-critical reactor, the swimming pool reactor is an existing research reactor in China Institute of Atomic Energy, its maximum output power is 3.5 MW. The effect of the instability of proton beam and possibility of simulation test on the verification facility have been analyzed

  13. Methods for reducing occupational exposures during the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1987-01-01

    The decommissioning and decontamination of nuclear facilities is a topic of great interest to many Member States of the International Atomic Energy Agency (IAEA) because of the large number of older facilities which have been or soon will be retired from service. This report is a review of the current state of knowledge concerning methods for reducing occupational exposures during the decommissioning of nuclear facilities. This report focuses on water cooled nuclear power plants but, in addition, other major nuclear facilities are briefly discussed to determine how they differ from nuclear power plants in this regard. The information presented should be useful to those responsible for or interested in designing or constructing nuclear facilities or in the planning or implementing of the decommissioning of such installations. 59 refs, 1 tab

  14. Air quality impacts due to construction of LWR waste management facilities

    International Nuclear Information System (INIS)

    1977-06-01

    Air quality impacts of construction activities and induced housing growth as a result of construction activities were evaluated for four possible facilities in the LWR fuel cycle: a fuel reprocessing facility, fuel storage facility, fuel fabrication plant, and a nuclear power plant. Since the fuel reprocessing facility would require the largest labor force, the impacts of construction of that facility were evaluated in detail

  15. Feedback experience from the decommissioning of Spanish nuclear facilities

    International Nuclear Information System (INIS)

    Santiago, J.L.

    2008-01-01

    The Spain has accumulated significant experience in the field of decommissioning of nuclear and radioactive facilities. Relevant projects include the remediation of uranium mills and mines, the decommissioning of research reactors and nuclear research facilities and the decommissioning of gas-graphite nuclear power plants. The decommissioning of nuclear facilities in Spain is undertaken by ENRESA, who is also responsible for the management of radioactive wastes. The two most notable projects are the decommissioning of the Vandellos I nuclear power plant and the decommissioning of the CIEMAT nuclear research centre. The Vandellos I power plant was decommissioned in about five years to what is known as level 2. During this period, the reactor vessel was confined, most plant systems and components were dismantled, the facility was prepared for a period of latency and a large part of the site was restored for subsequent release. In 2005 the facility entered into the phase of dormancy, with minimum operating requirements. Only surveillance and maintenance activities are performed, among which special mention should be made to the five-year check of the leak tightness of the reactor vessel. After the dormancy period (25 - 30 years), level 3 of decommissioning will be initiated including the total dismantling of the remaining parts of the plant and the release of the whole site for subsequent uses. The decommissioning of the CIEMAT Research Centre includes the dismantling of obsolete facilities such as the research reactor JEN-1, a pilot reprocessing plant, a fuel fabrication facility, a conditioning plant for liquid and a liquid waste storage facility which were shutdown in the early eighties. Dismantling works have started in 2006 and will be completed by 2009. On the basis of the experience gained in the above mentioned sites, this paper describes the approaches adopted by ENRESA for large decommissioning projects. (author)

  16. Electrical supervisory control and data acquisition system for Power Reactor Fuel Reprocessing Facility (PREFRE-II) at Tarapur

    International Nuclear Information System (INIS)

    Singh, V.K.; Kaushik, S.; Haneef, K.K.M.

    2014-01-01

    Power Reactor Fuel Reprocessing Facility (PREFRE II) is a radio-chemical plant located at Tarapur. The electric power supply to PREFRE-II plant has been provided from a 33 KV Sub-station located in PREFRE-II complex to meet the O and M requirement of plant. The major equipment of the substation includes HT switch board, dry type transformer, LT switch board, Diesel Generator (DG) set and Un-interrupted Power Supply (UPS) System. The power supply to the plant is provided at 415 V voltage level with the help of Power Distribution Boards (PDBs) and Motor Control Centres (MCCs) located at different floors of the plant. The parameters of the electrical equipment of substation and plant are recorded in each shift in the log-book, manually by the operator. To maintain the log-book, the operator needs to go closer to the individual equipment in radioactive area of the plant to read the parameters. The log-book method of monitoring is a cumbersome method and does not include fault event records, trends and diagnostic behavior of the equipment. Electrical Supervisory Control and Data Acquisition (E-SCADA) system has been increasingly used in Nuclear Power Plants (NPPs) for control and monitoring of electrical parameters of plant and switchyard equipment. E-SCADA system has been designed, developed and implemented for PREFRE-II plant for remote monitoring of parameters of electrical equipment. E-SCADA system provides monitoring of electrical equipment and renders complete guidance and information with the help of Graphical User Interface (GUI) to the operator to take necessary action during normal and abnormal conditions. E-SCADA with intelligent communication features helps in reducing cabling from field equipment which enhances the fire safety of plant. As a result engineering, operation and maintenance efforts for monitoring are reduced considerably in terms of requirement of skilled man power and accurate data logging of electrical parameters. This system also helps to

  17. Decommissioning of small medical, industrial and research facilities

    International Nuclear Information System (INIS)

    2003-01-01

    Most of the technical literature on decommissioning addresses the regulatory, organizational, technical and other aspects for large facilities such as nuclear power plants, reprocessing plants and relatively large prototype, research and test reactors. There are, however, a much larger number of licensed users of radioactive material in the fields of medicine, research and industry. Most of these nuclear facilities are smaller in size and complexity and may present a lower radiological risk during their decommissioning. Such facilities are located at research establishments, biological and medical laboratories, universities, medical centres, and industrial and manufacturing premises. They are often operated by users who have not been trained or are unfamiliar with the decommissioning, waste management and associated safety aspects of these types of facility at the end of their operating lives. Also, for many small users of radioactive material such as radiation sources, nuclear applications are a small part of the overall business or process and, although the operating safety requirements may be adhered to, concern or responsibility may not go much beyond this. There is concern that even the minimum requirements of decommissioning may be disregarded, resulting in avoidable delays, risks and safety implications (e.g. a loss of radioactive material and a loss of all records). Incidents have occurred in which persons have been injured or put at risk. It is recognized that the strategies and specific requirements for small facilities may be much less onerous than for large ones such as nuclear power plants or fuel processing facilities, but many of the same principles apply. There has been considerable attention given to nuclear facilities and many IAEA publications are complementary to this report. This report, however, attempts to give specific guidance for small facilities. 'Small' in this report does not necessarily mean small in size but generally modest in terms

  18. Decommissioning of Facilities. General Safety Requirements. Pt. 6

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-07-15

    Decommissioning is the last step in the lifetime management of a facility. It must also be considered during the design, construction, commissioning and operation of facilities. This publication establishes requirements for the safe decommissioning of a broad range of facilities: nuclear power plants, research reactors, nuclear fuel cycle facilities, facilities for processing naturally occurring radioactive material, former military sites, and relevant medical, industrial and research facilities. It addresses all the aspects of decommissioning that are required to ensure safety, aspects such as roles and responsibilities, strategy and planning for decommissioning, conduct of decommissioning actions and termination of the authorization for decommissioning. It is intended for use by those involved in policy development, regulatory control and implementation of decommissioning.

  19. Capsule safety analysis of PRTF irradiation facility

    International Nuclear Information System (INIS)

    Suwarto

    2013-01-01

    Power Ramp Test Facility (PRTF) is an irradiation facility used for fuel testing of power reactor. PRTF has a capsule which is a test fuel rod container. During operation, pressurized water of 160 bars flows through in the capsule. Due to the high pressure it should be analyzed the impact of the capsule on reactor core safety. This analysis has purpose to calculate the ability of capsule pressure capacity. The analysis was carried out by calculating pressure capacity. From the calculating results it can be concluded that the capsule with pressure capacity of 438 bars will be safe to prevent the operation pressure of PRTF. (author)

  20. Building a medical system for nuclear facilities

    International Nuclear Information System (INIS)

    Maeda, Mitsuya

    2016-01-01

    To build a medical system for nuclear facilities, I explained what kinds of actions were performed with the TEPCO Fukushima Daiichi Nuclear Power Plant Accident and what kinds of actions are going to be performed in the future. We examined the health and medical care of the emergency workers in nuclear facilities including TEPCO Fukushima Daiichi Nuclear Power Plant from 2014 to 2015 in the Ministry of Health, Labour and Welfare (MHLW). We carried out a detailed hearing from stakeholders of electric companies and medical institutions about the medical system in nuclear facilities carrying out urgent activities. It has been said that the electric company is responsible to maintain the medical system for affected workers in nuclear facilities. However, TEPCO could not find the medical staff, such as doctors, by their own effort at the TEPCO Fukushima Daiichi Nuclear Power Plant Accident. The network of doctors familiar with emergency medical care support dispatched the medical staff after July of 2011. The stakeholders indicated that the following six tasks must be resolved: (1) the fact that no electric company performs the action of bringing up medical staff who can be dispatched into nuclear facilities in emergencies in 2015; (2) bringing up personnel in charge of radiation management and logistics other than the medical staff, such as doctors; (3) cooperation with the community medicine system given the light and shade by nuclear facilities; (4) performing training for the many concurrent wounded based on the scenario of a severe accident; (5) indicating both the condition of the contract and the guarantee of status that is appropriate for dispatched medical staffs; and (6) clarifying the organization of the network of stakeholders. The stakeholders showed the future directionality as follows: (1) To recruit the medical staff expected to be dispatched into nuclear facilities, (2) to carry out the discussion and conveyance training to strengthen cooperation with

  1. Advanced Control Test Operation (ACTO) facility

    International Nuclear Information System (INIS)

    Ball, S.J.

    1987-01-01

    The Advanced Control Test Operation (ACTO) project, sponsored by the US Department of Energy (DOE), is being developed to enable the latest modern technology, automation, and advanced control methods to be incorporated into nuclear power plants. The facility is proposed as a national multi-user center for advanced control development and testing to be completed in 1991. The facility will support a wide variety of reactor concepts, and will be used by researchers from Oak Ridge National Laboratory (ORNL), plus scientists and engineers from industry, other national laboratories, universities, and utilities. ACTO will also include telecommunication facilities for remote users

  2. Design and development of embedded control system for high power RF test facility

    International Nuclear Information System (INIS)

    Nageswara Rao, J.; Badapanda, M.K.; Upadhyay, Rinki; Tripathi, Akhilesh; Hannurkar, P.R.

    2013-01-01

    Design and development of an embedded control system for the control, interlock and operation of 1MW, 352.2 MHz TH2089 klystron based RF test facility. The key components of the control system are NI compact Re configurable Input Output (cRIO) system and Windows based PC. The cRIO system's rugged hardware architecture includes a 1.06 GHz Dual-Core embedded controller with Real Time (RT) Operating System, a reconfigurable Field Programmable Gate Array (FPGA) chassis for custom I/O timing, control and processing; and I/O modules. Windows based Graphical User Interface (GUI) has been developed to guide the user through start-up procedure, to set the operating parameters and also to display the status information of all the signals. The application software for data logging and publishing of the acquired data namely set, read back and status signals of auxiliary power supplies and machine safety interlocks has been developed in LabVIEW RT module and is running on embedded controller. Machine safety interlock logic has been implemented in FPGA to meet the time criticality. (author)

  3. Regulations on allocating the sums of money regarding of development of radiation exposure reduction technology for nuclear power facilities

    International Nuclear Information System (INIS)

    1984-01-01

    The regulations provide for the sums of money regarding research and development of radiation exposure reduction technology for nuclear power facilities and evaluation of the results. Expenses cover the purchase of equipment, personnel expenditures, travelling expenses, communication, etc. The contents are as follows: the application for subsidy allocations, determination of subsidy allocations, withdrawal of applications, a report on the work proceedings, a report on the results, approval of alterations in the plans, withdrawal of the decision for a subsidy allocation, patent rights, utilization etc. of the results, management of the properties, etc. (Mori, K.)

  4. Nanofluidic crystal: a facile, high-efficiency and high-power-density scaling up scheme for energy harvesting based on nanofluidic reverse electrodialysis

    International Nuclear Information System (INIS)

    Ouyang Wei; Wang Wei; Zhang Haixia; Wu Wengang; Li Zhihong

    2013-01-01

    The great advances in nanotechnology call for advances in miniaturized power sources for micro/nano-scale systems. Nanofluidic channels have received great attention as promising high-power-density substitutes for ion exchange membranes for use in energy harvesting from ambient ionic concentration gradient, namely reverse electrodialysis. This paper proposes the nanofluidic crystal (NFC), of packed nanoparticles in micro-meter-sized confined space, as a facile, high-efficiency and high-power-density scaling-up scheme for energy harvesting by nanofluidic reverse electrodialysis (NRED). Obtained from the self-assembly of nanoparticles in a micropore, the NFC forms an ion-selective network with enormous nanochannels due to electrical double-layer overlap in the nanoparticle interstices. As a proof-of-concept demonstration, a maximum efficiency of 42.3 ± 1.84%, a maximum power density of 2.82 ± 0.22 W m −2 , and a maximum output power of 1.17 ± 0.09 nW/unit (nearly three orders of magnitude of amplification compared to other NREDs) were achieved in our prototype cell, which was prepared within 30 min. The current NFC-based prototype cell can be parallelized and cascaded to achieve the desired output power and open circuit voltage. This NFC-based scaling-up scheme for energy harvesting based on NRED is promising for the building of self-powered micro/nano-scale systems. (paper)

  5. Design requirements for new nuclear reactor facilities in Canada

    International Nuclear Information System (INIS)

    Shim, S.; Ohn, M.; Harwood, C.

    2012-01-01

    The Canadian Nuclear Safety Commission (CNSC) has been establishing the regulatory framework for the efficient and effective licensing of new nuclear reactor facilities. This regulatory framework includes the documentation of the requirements for the design and safety analysis of new nuclear reactor facilities, regardless of size. For this purpose, the CNSC has published the design and safety analysis requirements in the following two sets of regulatory documents: 1. RD-337, Design of New Nuclear Power Plants and RD-310, Safety Analysis for Nuclear Power Plants; and 2. RD-367, Design of Small Reactor Facilities and RD-308, Deterministic Safety Analysis for Small Reactor Facilities. These regulatory documents have been modernized to document past practices and experience and to be consistent with national and international standards. These regulatory documents provide the requirements for the design and safety analysis at a high level presented in a hierarchical structure. These documents were developed in a technology neutral approach so that they can be applicable for a wide variety of water cooled reactor facilities. This paper highlights two particular aspects of these regulatory documents: The use of a graded approach to make the documents applicable for a wide variety of nuclear reactor facilities including nuclear power plants (NPPs) and small reactor facilities; and, Design requirements that are new and different from past Canadian practices. Finally, this paper presents some of the proposed changes in RD-337 to implement specific details of the recommendations of the CNSC Fukushima Task Force Report. Major changes were not needed as the 2008 version of RD-337 already contained requirements to address most of the lessons learned from the Fukushima event of March 2011. (author)

  6. Status of spent fuel storage facilities in Switzerland

    International Nuclear Information System (INIS)

    Beyeler, P.C.; Lutz, H.R.; Heesen, W. von

    1999-01-01

    Planning of a dry spent fuel storage facility in Switzerland started already 15 years ago. The first site considered for a central interim storage facility was the cavern of the decommissioned pilot nuclear plant at Lucens in the French-speaking part of Switzerland. This project was terminated in the late eighties because of lack of public acceptance. The necessary acceptance was found in the small town of Wuerenlingen which has hosted for many years the Swiss Reactor Research Centre. The new project consists of centralised interim storage facilities for all types of radioactive waste plus a hot cell and a conditioning and incinerating facility. It represents a so-called integrated storage solution. In 1990, the new company 'ZWILAG Zwischenlager Wuerenlingen AG' (ZWILAG) was founded and the licensing procedures according to the Swiss Atomic law were initiated. On August 26, 1996 ZWILAG got the permit for construction of the whole facility including the operating permit for the storage facilities. End of construction and commissioning are scheduled for autumn 1999. The nuclear power station Beznau started planning a low level waste and spent fuel storage facility on its own, because in 1990 its management thought that by 1997 the first high active waste from the reprocessing facilities in France would have to be taken back. This facility at the Beznau site, called ZWIBEZ, was licensed according to a shorter procedure so its construction was finished by 1997. The two facilities for high level waste and spent fuel provide space for a total of 278 casks, which is sufficient for the waste and spent fuel of the four Swiss nuclear power stations including their life extension programme. (author)

  7. Fuel Cells for Backup Power in Telecommunications Facilities (Fact Sheet)

    Energy Technology Data Exchange (ETDEWEB)

    2009-04-01

    Telecommunications providers rely on backup power to maintain a constant power supply, to prevent power outages, and to ensure the operability of cell towers, equipment, and networks. The backup power supply that best meets these objectives is fuel cell technology.

  8. Hydroelectric power in Switzerland: large growth potential by increasing the installed power

    International Nuclear Information System (INIS)

    Schleiss, A.

    2007-01-01

    Due to its important hydroelectric power generation facilities (about 525 plants with a total power of 13,314 MW producing about 35.3 TWh annually) Switzerland plays an important role in the interconnected European power system. Large artificial storage lakes in the Swiss Alps can generate peak power during hours of highest demand: 9700 MW are available from accumulated energy and the total power of pumped-storage facilities amounts to 1700 MW. The latter allow refilling the reservoirs at periods of low power demand and generating power at periods of peak demand. In the case of favorable conditions, the yearly average power production could be increased by 6% and the production during the winter period (October to March) by 20% by the year 2020. However, looking forward to the year 2050, the annual production is expected to decrease by 3% despite a possible extension of hydropower. This decrease is due to the enforcement of the minimum residual water flow rates required by a new legislation to protect the rivers. The enforcement is due at latest when the present licenses for water utilization expire. On the other hand, the installed (peak) power might be further increased by 50% by retrofitting the existing installations and constructing the pumped-storage plants currently at the planning stage

  9. Electrical energy and cost for the Mirror Fusion Test Facility

    International Nuclear Information System (INIS)

    Pence, G.A.

    1983-02-01

    An operational scenario for the Mirror Fusion Test Facility has been developed based on System Requirements, experience with existing systems, and discussions with project engineers and designers who are responsible for the systems. This scenario was used to project the electrical energy required for the facility. Each system is listed showing the equipment that has been considered, the amount of power requested, and in most cases, the power that it is now connected

  10. Subcritical neutron generator-test facility for nuclear waste transmutation studies

    Energy Technology Data Exchange (ETDEWEB)

    Chuvilo, I.V.; Kolomiets, A.A.; Kozodaev, A.M. [ITEP, Moscow (Russian Federation)] [and others

    1995-10-01

    The development of the optimal design of high power facility for NPP transmutation and for a number of applications can not be carried out without preliminary tests of much cheaper prototypes. It has been proposed to combine in new test facility 36 MeV Linac ISTRA constructed in ITEP, original Be target and subcritical blanket that will be mounted on the place of partly disassembled heavy water ITEP experimental reactor. The basic parameters of Linac, schemes of the target and blanket are described. It will provide the direct experiments on installation which can be considered as prototype for future linac driven high power facilities.

  11. Stored energy analysis in the scaled-down test facilities

    International Nuclear Information System (INIS)

    Deng, Chengcheng; Chang, Huajian; Qin, Benke; Wu, Qiao

    2016-01-01

    Highlights: • Three methods are developed to evaluate stored energy in the scaled-down test facilities. • The mechanism behind stored energy distortion in the test facilities is revealed. • The application of stored energy analysis is demonstrated for the ACME facility of China. - Abstract: In the scaled-down test facilities that simulate the accident transient process of the prototype nuclear power plant, the stored energy release in the metal structures has an important influence on the accuracy and effectiveness of the experimental data. Three methods of stored energy analysis are developed, and the mechanism behind stored energy distortion in the test facilities is revealed. Moreover, the application of stored energy analysis is demonstrated for the ACME test facility newly built in China. The results show that the similarity requirements of three methods analyzing the stored energy release decrease gradually. The physical mechanism of stored energy release process can be characterized by the dimensionless numbers including Stanton number, Fourier number and Biot number. Under the premise of satisfying the overall similarity of natural circulation, the stored energy release process in the scale-down test facilities cannot maintain exact similarity. The results of the application of stored energy analysis illustrate that both the transient release process and integral total stored energy of the reactor pressure vessel wall of CAP1400 power plant can be well reproduced in the ACME test facility.

  12. ASSESSMENT OF COMBINED HEAT AND POWER SYSTEM"PREMIUM POWER" APPLICATIONS IN CALIFORNIA

    Energy Technology Data Exchange (ETDEWEB)

    Norwood, Zack; Lipman, Timothy; Stadler, Michael; Marnay, Chris

    2010-06-01

    The effectiveness of combined heat and power (CHP) systems for power interruption intolerant,"premium power," facilities is the focus of this study. Through three real-world case studies and economic cost minimization modeling, the economic and environmental performance of"premium power" CHP is analyzed. The results of the analysis for a brewery, data center, and hospital lead to some interesting conclusions about CHP limited to the specific CHP technologies installed at those sites. Firstly, facilities with high heating loads prove to be the most appropriate for CHP installations from a purely economic standpoint. Secondly, waste heat driven thermal cooling systems are only economically attractive if the technology for these chillers can increase above the current best system efficiency. Thirdly, if the reliability of CHP systems proves to be as high as diesel generators they could replace these generators at little or no additional cost if the thermal to electric (relative) load of those facilities was already high enough to economically justify a CHP system. Lastly, in terms of greenhouse gas emissions, the modeled CHP systems provide some degree of decreased emissions, estimated at approximately 10percent for the hospital, the application with the highest relative thermal load in this case

  13. Power supply control system for experimental physical facilities

    International Nuclear Information System (INIS)

    Zelepukin, S.A.; Osipov, Eh.V.; Petrov, V.S.; Sergeev, V.A.; Uglekov, V.Ya.

    1979-01-01

    A multichannel (to 1024 channels) system for control of power supply voltage is descrited. The system consists of an analog commulator, a digital voltmeter and a special controller. The controller serves at the same time as an interface for connecting the system as a ''unit'' of the VECTOR and SUMMA unified electronic systems. The system has been realized for control of the photomultiplier power supply voltage of the MARK multipurpose experimental device (256 channels, the measurement accuracy is 0.2%, the measuring time is 500 ms per point). Software devised for the HP-2100 computer permits automatical comparison of photomultiplier power supply voltages with sample ones in the mode of continuous control of a single voltage or in the mode of programmed selection of voltages to provide the control in arbitrary order or automatic scanning

  14. Design for the second phase Rokkasho LLW burial facility

    International Nuclear Information System (INIS)

    Kumata, Tadamasa

    1997-01-01

    Rokkasho Low Level radioactive Waste management center of Japan Nuclear Fuel Limited (hereafter called JNFL) has been operating for five years and about 90,000 (200 liter) drums have already been buried. Currently, JNFL is planning the 2nd phase of the burial program. The basic design of the new facility has been completed and applied for license additionally. Wastes buried in the 2nd phase facility are mainly dry active wastes from nuclear power plants. Inflammable wastes except for plastics are incinerated before they are disposed, because organic materials can generate gas and their degraded materials affect the distribution coefficients of the radionuclides. Most of the aluminum wastes which can generate hydrogen gas by corrosion are also removed from the waste. The 2nd phase facility accepts metal, plastics and non-flammable wastes. These are solidified with mortar in the 200 liter drums at the power plants. The radioactive inventory of the 2nd phase facility is considered to be as much as that of the 1st phase facility. (author)

  15. Detection of fatigue damage of high and medium pressure rotor by X-ray diffraction method. Survey and research of nondestructive examination of thermal power generation facilities

    Energy Technology Data Exchange (ETDEWEB)

    Yamamoto, Tatsuo; Suesada, Yasuhiko; Nishioka, Noriaki; Goto, Toru; Ito, Hitomi; Kadoya, Yoshikuni

    1987-03-25

    In recent years, the existing thermal power generation facilities have been required to be operated in securing dependability from the standpoints of the operating conditions which have been getting severer and the demands to use them for longer periods, accordingly it is hoped to establish the diagnostic technology of aged deterioration by the non-destructive examination method for the facilities. In the beginning of 1959 the Kansai Electric Power Co. surveyed the current situation of this technology at various thermal power generation turbine facilities and discovered that concerning the diagnostic technology of aged deterioration by the non-destructive examination method, there remained many matters untouched in the basic research field. The company consequently started a survey and research jointly with Mitsubishi Heavy Industries in the first half of 1959. This report summarizes the research on the detection of aged deterioration due to thermal fatigue of Cr-Mo-V rotor material by the X-ray diffraction method which was conducted during the full fiscal year of 1984 and the first half of FY 1985 as a part of the above joint research. With respect to the conditions for the detection method of thermal fatigue damages of dummy grooves of the high and medium pressure rotor by the application of the X-ray diffraction method, it is preferred to measure a diffraction strength curve of the diffraction surface by using a Co tube as X-ray tube and it is also desirable to use a position sensitive proportional counter tube for X-ray detector. (5 figs, 6 refs)

  16. Policies to deal with reactionary factors in the location of nuclear power facilities

    International Nuclear Information System (INIS)

    Lee, Yong Soo

    2000-01-01

    Energy is very important for daily life. But the prevailing fossil fuels are almost running out and moore over, the global warming caused by fossil fuel threatens all lives on the earth. Yet in reality, there are almost no choices to take the place fossil fuels beside nuclear energy. Nuclear energy is the only practical new energy resource that can be produced in Korea, which possesses nearly no energy resources and imports 98% do its energy supplies annually. Fortunately the rate of self-reliance of Korean nuclear technology is up to 95%, which is almost at top level in the world. However, many people think that nuclear energy is dangerous and uneconomical, thus social tension and dispute often a rises regarding nuclear energy, To minimize these discords, those in charge of the facility should provide an acceptable strategy to the publics, especially concerning the location of the facility. The strategy should include the followings: (1) The publics should participate in the planning stage of the nuclear facility, not only symbolically but also practically, and all information should be opened to publics so that cost-effectiveness and safety of the facility can be evaluated. (2) For the people who lose their land, home and work, an appropriate compensation should be considered from the planning stage. (3) The person in charge of the facility has to show that people in neighborhood of the facility enjoy better life than before and should help people to recognize it. (4) Continuous campaign enhancing public understanding of the need and safety for nuclear facility must be implemented. (5) South Korea's nuclear facilities could be set up in North Korea as the relationships between two Koreas improve. (author)

  17. D. C. power supply

    Energy Technology Data Exchange (ETDEWEB)

    Ohashi, N. Watanabe, Y.; Kitani, M

    1978-04-01

    DC power supplies are for ordinary and emergency use as power sources for various structures such as office buildings, department stores, hotels, and for facilities such as roads, tunnels, dams, power stations, etc. There is strong demand for these dc power supplies to be safe, automated, and maintenance free, and to have high reliability. A dc power supply which meets these demands is described; electric circuit construction is emphasized. (10 figures, 4 tables)

  18. Applicability of Long Duration Exposure Facility environmental effects data to the design of Space Station Freedom electrical power system

    Science.gov (United States)

    Christie, Robert J.; Lu, Cheng-Yi; Aronoff, Irene

    1992-01-01

    Data defining space environmental effects on the Long Duration Exposure Facility (LDEF) are examined in terms of the design of the electrical power system (EPS) of the Space Station Freedom (SSF). The significant effects of long-term exposure to space are identified with respect to the performance of the LDEF's materials, components, and systems. A total of 57 experiments were conducted on the LDEF yielding information regarding coatings, thermal systems, electronics, optics, and power systems. The resulting database is analyzed in terms of the specifications of the SSF EPS materials and subsystems and is found to be valuable in the design of control and protection features. Specific applications are listed for findings regarding the thermal environment, atomic oxygen, UV and ionizing radiation, debris, and contamination. The LDEF data are shown to have a considerable number of applications to the design and planning of the SSF and its EPS.

  19. Ventilation and air conditioning system in waste treatment and storage facilities

    International Nuclear Information System (INIS)

    Kinoshita, Hirotsugu; Sugawara, Kazushige.

    1987-01-01

    So far, the measures concerning the facilities for treating and storing radioactive wastes in nuclear fuel cycle in Japan were in the state which cannot be said to be sufficient. In order to cope with this situation, electric power companies constructed and operated radioactive waste concentration and volume reduction facilities, solid waste storing facilities for drums, high level solid waste storing facilities, spent fuel cask preserving facilities and so on successively in the premises of nuclear power stations, and for the wastes expected in future, the research and the construction plan of the facilities for treating and storing low, medium and high level wastes have been advanced. The ventilation and air conditioning system for these facilities is the important auxiliary system which has the mission of maintaining safe and pleasant environment in the facilities and lowering as far as possible the release of radioactive substances to outside. The outline of waste treatment and storage facilities is explained. The design condition, ventilation and air conditioning method, the features of respective waste treatment and storage facilities, and the problems for the future are described. Hereafter, mechanical ventilation system continues to be the main system, and filters become waste, while the exchange of filters is accompanied by the radiation exposure of workers. (Kako, I.)

  20. Lunar Wireless Power Transfer Feasibility Study

    Energy Technology Data Exchange (ETDEWEB)

    Freid, Sheldon [National Security Technologies, LLC. (NSTec), Mercury, NV (United States); Popovic, Zoya [Univ. of Colorado, Boulder, CO (United States); Beckett, David R. [Independent Consultant; Anderson, Scott R. [Independent Consultant; Mann, Diana [Independent Consultant; Walker, Stuart [Independent Consultant

    2008-03-01

    This study examines the feasibility of a multi-kilowatt wireless radio frequency (RF) power system to transfer power between lunar base facilities. Initial analyses, show that wireless power transfer (WPT) systems can be more efficient and less expensive than traditional wired approaches for certain lunar and terrestrial applications. The study includes evaluations of the fundamental limitations of lunar WPT systems, the interrelationships of possible operational parameters, and a baseline design approach for a notionial system that could be used in the near future to power remote facilities at a lunar base. Our notional system includes state-of-the-art photovoltaics (PVs), high-efficiency microwave transmitters, low-mass large-aperture high-power transmit antennas, high-efficiency large-area rectenna receiving arrays, and reconfigurable DC combining circuitry.

  1. Study of electrical power facilities and measures for planned outages in Japanese hemodialysis clinics after the Great East Japan Earthquake.

    Science.gov (United States)

    Ishida, Kai; Sawa, Manami; Fujiwara, Kousaku; Hirose, Minoru; Tsuruta, Harukazu; Takeuchi, Akihiro; Ikeda, Noriaki

    2013-02-01

    The Great East Japan Earthquake on 11 March 2011 caused major damage in northeastern Japan. The Kanto region experienced a massive electrical power shortage in the summer of 2011. A questionnaire was submitted to 354 hemodialysis clinics in Kanagawa prefecture and the Tokyo metropolitan area, excluding isolated islands, and 176 responses were analyzed (49.7%). The questions included evaluation of the availability of a private electricity generator, countermeasures in case of a planned outage, awareness of saving electricity, and improvement of safety of medical devices or electrical facilities after the earthquake. Only 12% of the clinics had private electricity generators and many clinics had no plans to introduce this facility. However, 96% of the clinics had established countermeasures to deal with a planned outage. Many clinics planned to provide dialysis on a different day or at a different time. All clinics had tried hard to establish procedures to save electricity in the summer of 2011, and 84% of the clinics had reconsidered and improved the safety of medical devices or electricity facilities after the earthquake. These results show that the awareness of crisis management was greatly improved in the wake of the earthquake. © 2012 The Authors. Therapeutic Apheresis and Dialysis © 2012 International Society for Apheresis.

  2. Seismic analysis for shroud facility in-pile tube and saturated temperature capsules

    International Nuclear Information System (INIS)

    Iimura, Koichi; Yamaura, Takayuki; Ogawa, Mitsuhiro

    2009-07-01

    At Oarai Research and Development Center, Japan Atomic Energy Agency (JAEA), the plan of repairing and refurbishing Japan Materials Testing Reactor (JMTR) has progressed in order to restart JMTR operation in the fiscal 2011. As a part of effective use of JMTR, the neutron irradiation tests of LWR fuels and materials has been planned in order to study their soundness. By using Oarai Shroud Facility (OSF-1) and Fuel Irradiation Facility with the He-3 gas control system for power lamping test using Boiling Water Capsules (BOCA Irradiation Facility), the irradiation tests with power ramping will be carried out to study the soundness of fuel under LWR Transient condition. OSF-1 is the irradiation facility of shroud type that can insert and eject the capsule under reactor operation, and is composed of 'In-pile Tube', 'Cooling system' and 'Capsule exchange system'. BOCA Irradiation Facility is the facility which simulates irradiation environment of LWR, and is composed of 'Boiling water Capsule', 'Capsule control system' and 'Power control system by He-3'. By using Saturated temperature Capsules and the water environment control system, the material irradiation tests under the water chemistry condition of LWR will be carried out to clarify the mechanism of IASCC. In JMTR, these facilities are in service at the present. However, the detailed design for renewal or remodeling was carried out based on the new design condition in order to be correspondent to the irradiation test plan after restart JMTR operation. In this seismic analysis of the detailed design, each equipment classification and operating state were arranged with 'Japanese technical standards of the structure on nuclear facility for test research' and 'Technical guidelines for seismic design of nuclear power plants on current, and then, stress calculation and evaluation were carried out by FEM piping analysis code 'SAP' and structure analysis code 'ABAQUS'. About the stress of the seismic force, it was proven

  3. Thermionic system evaluated test (TSET) facility description

    Science.gov (United States)

    Fairchild, Jerry F.; Koonmen, James P.; Thome, Frank V.

    1992-01-01

    A consortium of US agencies are involved in the Thermionic System Evaluation Test (TSET) which is being supported by the Strategic Defense Initiative Organization (SDIO). The project is a ground test of an unfueled Soviet TOPAZ-II in-core thermionic space reactor powered by electrical heat. It is part of the United States' national thermionic space nuclear power program. It will be tested in Albuquerque, New Mexico at the New Mexico Engineering Research Institute complex by the Phillips Laboratoty, Sandia National Laboratories, Los Alamos National Laboratory, and the University of New Mexico. One of TSET's many objectives is to demonstrate that the US can operate and test a complete space nuclear power system, in the electrical heater configuration, at a low cost. Great efforts have been made to help reduce facility costs during the first phase of this project. These costs include structural, mechanical, and electrical modifications to the existing facility as well as the installation of additional emergency systems to mitigate the effects of utility power losses and alkali metal fires.

  4. Environmental Protection Agency (EPA) Facility Registry Service (FRS) Power Plants

    Data.gov (United States)

    Department of Homeland Security — This GIS dataset contains data on wastewater treatment plants, based on EPA's Facility Registry Service (FRS) and NPDES, along with Clean Watersheds Needs Survey...

  5. Remote handling technology for nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Sakai, Akira; Maekawa, Hiromichi; Ohmura, Yutaka

    1997-01-01

    Design and R and D on nuclear fuel cycle facilities has intended development of remote handling and maintenance technology since 1977. IHI has completed the design and construction of several facilities with remote handling systems for Power Reactor and Nuclear Fuel Development Corporation (PNC), Japan Atomic Energy Research Institute (JAERI), and Japan Nuclear Fuel Ltd. (JNFL). Based on the above experiences, IHI is now undertaking integration of specific technology and remote handling technology for application to new fields such as fusion reactor facilities, decommissioning of nuclear reactors, accelerator testing facilities, and robot simulator-aided remote operation systems in the future. (author)

  6. Preliminary design for a maglev development facility

    Energy Technology Data Exchange (ETDEWEB)

    Coffey, H.T.; He, J.L.; Chang, S.L.; Bouillard, J.X.; Chen, S.S.; Cai, Y.; Hoppie, L.O.; Lottes, S.A.; Rote, D.M. (Argonne National Lab., IL (United States)); Zhang, Z.Y. (Polytechnic Univ., Brooklyn, NY (United States)); Myers, G.; Cvercko, A. (Sterling Engineering, Westchester, IL (United States)); Williams, J.R. (Alfred Benesch and Co., Chicago, IL (United States))

    1992-04-01

    A preliminary design was made of a national user facility for evaluating magnetic-levitation (maglev) technologies in sizes intermediate between laboratory experiments and full-scale systems. A technical advisory committee was established and a conference was held to obtain advice on the potential requirements of operational systems and how the facility might best be configured to test these requirements. The effort included studies of multiple concepts for levitating, guiding, and propelling maglev vehicles, as well as the controls, communications, and data-acquisition and -reduction equipment that would be required in operating the facility. Preliminary designs for versatile, dual 2-MVA power supplies capable of powering attractive or repulsive systems were developed. Facility site requirements were identified. Test vehicles would be about 7.4 m (25 ft) long, would weigh form 3 to 7 metric tons, and would operate at speeds up to 67 m/s (150 mph) on a 3.3-km (2.05-mi) elevated guideway. The facility would utilize modular vehicles and guideways, permitting the substitution of levitation, propulsion, and guideway components of different designs and materials for evaluation. The vehicle would provide a test cell in which individual suspension or propulsion components or subsystems could be tested under realistic conditions. The system would allow economical evaluation of integrated systems under varying weather conditions and in realistic geometries.

  7. Stored energy analysis in scale-down test facility

    International Nuclear Information System (INIS)

    Deng Chengcheng; Qin Benke; Fang Fangfang; Chang Huajian; Ye Zishen

    2013-01-01

    In the integral test facilities that simulate the accident transient process of the prototype nuclear power plant, the stored energy in the metal components has a direct influence on the simulation range and the test results of the facilities. Based on the heat transfer theory, three methods analyzing the stored energy were developed, and a thorough study on the stored energy problem in the scale-down test facilities was further carried out. The lumped parameter method and power integration method were applied to analyze the transient process of energy releasing and to evaluate the average total energy stored in the reactor pressure vessel of the ACME (advanced core-cooling mechanism experiment) facility, which is now being built in China. The results show that the similarity requirements for such three methods to analyze the stored energy in the test facilities are reduced gradually. Under the condition of satisfying the integral similarity of natural circulation, the stored energy releasing process in the scale-down test facilities can't maintain exact similarity. The stored energy in the reactor pressure vessel wall of ACME, which is released quickly during the early stage of rapid depressurization of system, will not make a major impact on the long-term behavior of system. And the scaling distortion of integral average total energy of the stored heat is acceptable. (authors)

  8. Technical Proposal Salton Sea Geothermal Power Pilot Plant Program

    Energy Technology Data Exchange (ETDEWEB)

    None

    1975-03-28

    The proposed Salton Sea Geothermal Power Pilot Plant Program comprises two phases. The objective of Phase 1 is to develop the technology for power generation from high-temperature, high-salinity geothermal brines existing in the Salton Sea known geothermal resources area. Phase 1 work will result in the following: (a) Completion of a preliminary design and cost estimate for a pilot geothermal brine utilization facility. (b) Design and construction of an Area Resource Test Facility (ARTF) in which developmental geothermal utilization concepts can be tested and evaluated. Program efforts will be divided into four sub-programs; Power Generation, Mineral Extraction, Reservoir Production, and the Area Resources Test Facility. The Power Generation Subprogram will include testing of scale and corrosion control methods, and critical power cycle components; power cycle selection based on an optimization of technical, environmental and economic analyses of candidate cycles; preliminary design of a pilot geothermal-electric generating station to be constructed in Phase 2 of this program. The Mineral Extraction Subprogram will involve the following: selection of an optimum mineral recovery process; recommendation of a brine clean-up process for well injection enhancement; engineering, construction and operation of mineral recovery and brine clean-up facilities; analysis of facility operating results from environmental, economical and technical point-of-view; preliminary design of mineral recovery and brine clean-up facilities of sufficient size to match the planned pilot power plant. The Reservoir Production Subprogram will include monitoring the operation and maintenance of brine production, handling and injection systems which were built with private funding in phase 0, and monitoring of the brine characteristics and potential subsidence effects during well production and injection. Based on the above, recommendations and specifications will be prepared for production and

  9. Small scale wind power harnessing in Colombian oil industry facilities: Wind resource and technology issues

    Energy Technology Data Exchange (ETDEWEB)

    Giraldo, Mauricio; Nieto, Cesar; Escudero, Ana C.; Cobos, Juan C.; Delgado, Fernando

    2010-07-01

    Full text: Looking to improve its national and international standing, Colombia's national oil company, Ecopetrol, has set its goal on becoming involved on the production of energy from multiple sources, most importantly, on having an important percentage of its installed capacity from renewable sources. Part of this effort entices the evaluation of wind power potential on its facilities, including production, transportation and administrative, as well as identifying those technologies most suitable for the specific conditions of an equatorial country such as Colombia. Due to the lack of adequate site information, the first step consisted in superimposing national data to the facilities map of the company; this allowed for the selection of the first set of potential sites. From this set, the terminal at Covenas-Sucre was selected taking into account not only wind resource, but ease of access and power needs, as well as having a more or less representative wind potential in comparison to the rest of the country. A weather station was then installed to monitor wind variables. Measurements taken showed high variations in wind direction, and relatively low velocity profiles, making most commercially available wind turbines difficult to implement. In light of the above, a series of iterative steps were taken, first considering a range of individual Vertical Axis Wind Turbines (VAWT), given their capacity to adapt to changing wind directions. However, wind speed variations proved to be a challenge for individual VAWT's, i.e. Darriues turbines do not work well with low wind speeds, and Savonius turbines are not efficient of high wind speeds. As a result, a combined Darrieus- Savonius VAWT was selected given the capacity to adapt to both wind regimes, while at the same time modifying the size and shape of the blades in order to adapt to the lower average wind speeds present at the site. The resulting prototype is currently under construction and is scheduled to

  10. Regulatory control of nuclear facility valves and their actuators

    International Nuclear Information System (INIS)

    1993-01-01

    The methods and procedures by which the Finnish Centre for Radiation and Nuclear Safety (STUK) regulates valves and their actuators in nuclear power plants and in other nuclear facilities are specified in the guide. The scope of regulation depends on the Safety Class of the valve and the actuator in question. The Safety Classification principles for the systems, structures and components of the nuclear power plants are described in the guide YVL 2.1 and the regulatory control of the nuclear facility safety valves is described in the guide YVL 5.4

  11. Safety evaluation of the loss of fluid test facility project No. 394

    International Nuclear Information System (INIS)

    1975-05-01

    Assessment of the safety of the LOFT facility and subsequent recommendations have been based on a comparison of the LOFT facility to requirements for commercial power reactors. In this comparison, the many unique features of the LOFT facility were considered including the low power level, the limited operational use as a test reactor, and the remoteness of the site. Based on this assessment, it is concluded, that while the likelihood of an accidental release of fission products may be greater than for a commercial power reactor, the consequences of such a release are reduced by the lower fission product inventory, the remoteness of the site and the capability of evacuating the Idaho National Engineering Laboratory (INEL) and adjacent areas. There is reasonable assurance that the public health and safety will not be endangered due to operation of this facility, specifically: The INEL site is acceptable with respect to location, land use, population distribution, controlled access, hydrology, meteorology, geology and seismology. Sufficient engineered safety features have been included to assure that the potential offsite doses are well within 10 CFR Part 100 guidelines. The LOFT facility has been designed in general accordance with standards, guides and codes which are comparable to those applied to commercial power reactors and any exceptions to these have been based on the unique features of the LOFT facility. Certain matters including the final safety analyses based on detailed component designs, Technical Specifications, LOCE controls and detailed program plan have not been reviewed but we assume will properly be resolved by ERDA, which has the ultimate responsibility for the safety of this facility. Changes to the facility design or program plan such as removal of the fueled Mobile Test Assembly or blowdowns to the containment vessel also will require additional analyses and review. (U.S.)

  12. Power engineering and turbine manufacture in Japan. Pt. 2

    International Nuclear Information System (INIS)

    Troyanovskij, B.M.

    1995-01-01

    Vapour turbines designs of thermal power plants, including those with increased steam parameters, nuclear power plants, vapour-gas facilities are considered. Data on efficiency of turbofacilities, turbinesmaterials, maneuverability characteristics, releases from gas-turbine facilities are presented. 21 refs.; 6 figs.; 5 tabs

  13. Current status of irradiation facilities in JRR-3 and JRR-4

    International Nuclear Information System (INIS)

    Hori, Naohiko; Wada, Shigeru; Sasajima, Fumio; Kusunoki, Tsuyoshi

    2006-01-01

    The Department of Research Reactor has operated two research reactors, JRR-3 and JRR-4. These reactors were constructed in the Tokai Research Establishment. Many researchers and engineers use these joint-use facilities. JRR-3 is a light water moderated and cooled, pool type research reactor using low-enriched silicide fuel. JRR-3's maximum thermal power is 20MW. JRR-3 has nine vertical irradiation holes for RI production, nuclear fuels and materials irradiation at reactor core area. JRR-3 has many kinds of irradiation holes in a heavy water tank around the reactor core. These are two hydraulic rabbit irradiation facilities, two pneumatic rabbit irradiation facilities, one activation analysis irradiation facilities, one uniform irradiation facility, one rotating irradiation facility and one capsule irradiation facility. JRR-3 has nine horizontal experimental holes, that are used by many kinds of neutron beam experimental facilities using these holes. JRR-4 is a light water moderated and cooled, swimming pool type research reactor using low-enriched silicide fuel. JRR-4's maximum thermal power is 3.5MW. JRR-4 has five vertical irradiation tubes at reactor core area, three capsule irradiation facilities, one hydraulic rabbit irradiation facility, and one pneumatic rabbit irradiation facility. JRR-4 has a neutron beam hole, and it has used neutron beam experiments, irradiations for activation analysis and medical neutron irradiations. (author)

  14. Microcomputer simulation model for facility performance assessment: a case study of nuclear spent fuel handling facility operations

    International Nuclear Information System (INIS)

    Chockie, A.D.; Hostick, C.J.; Otis, P.T.

    1985-10-01

    A microcomputer based simulation model was recently developed at the Pacific Northwest Laboratory (PNL) to assist in the evaluation of design alternatives for a proposed facility to receive, consolidate and store nuclear spent fuel from US commercial power plants. Previous performance assessments were limited to deterministic calculations and Gantt chart representations of the facility operations. To insure that the design of the facility will be adequate to meet the specified throughput requirements, the simulation model was used to analyze such factors as material flow, equipment capability and the interface between the MRS facility and the nuclear waste transportation system. The simulation analysis model was based on commercially available software and application programs designed to represent the MRS waste handling facility operations. The results of the evaluation were used by the design review team at PNL to identify areas where design modifications should be considered. 4 figs

  15. Childhood leukaemia around Canadian nuclear facilities. Phase 1

    International Nuclear Information System (INIS)

    Clarke, E.A.; McLaughlin, J.; Anderson, T.W.

    1989-05-01

    A ninefold excess risk of leukaemia, as observed in vicinity of the Sellafield facility, was not observed amongst children born to mothers residing in the areas around nuclear research facilities and uranium mining, milling and refining facilities in Ontario. In the vicinity of nuclear research facilities, the rate of leukaemia was, in fact, less than expected. In the areas around the uranium mining, milling and refining facilities; leukaemia occurred slightly more frequently than expected; however, due to small frequencies these results may have risen by chance. A slightly greater than expected occurrence of leukaemia was also detected, which may well have been due to chance, in an exploratory study of the areas around nuclear power generating stations in Ontario

  16. Design of spent fuel storage facilities

    International Nuclear Information System (INIS)

    1994-01-01

    This Safety Guide is for interim spent fuel storage facilities that are not integral part of an operating nuclear power plant. Following the introduction, Section 2 describes the general safety requirements applicable to the design of both wet and dry spent fuel storage facilities; Section 3 deals with the design requirements specific to either wet or dry storage. Recommendations for the auxiliary systems of any storage facility are contained in Section 4; these are necessary to ensure the safety of the system and its safe operation. Section 5 provides recommendations for establishing the quality assurance system for a storage facility. Section 6 discusses the requirements for inspection and maintenance that must be considered during the design. Finally, Section 7 provides guidance on design features to be considered to facilitate eventual decommissioning. 18 refs

  17. Description of the PIE facility for research reactors irradiated fuels in CNEA

    International Nuclear Information System (INIS)

    Bisca, A.; Coronel, R.; Homberger, V.; Quinteros, A.; Ratner, M.

    2002-01-01

    The PIE Facility (LAPEP), located at the Ezeiza Atomic Center (CAE), was designed to carry out destructive and non-destructive post-irradiation examinations (PIE) on research and power reactor spent fuels, reactor internals and other irradiated materials, and to perform studies related with: Station lifetime extension; Fuel performance; Development of new fuels; and Failures and determination of their causes. LAPEP is a relevant facility where research and development can be carried out. It is worth mentioning that in this facility the PIE corresponding to the Surveillance Program for the Atucha I Nuclear Power Plant (CNA-1) were successfully performed. Materials testing during the CNA-1 repair and the study of failures in fuel element plugs of the Embalse Nuclear Power Plant (CNE) were also performed. (author)

  18. Impact of Distributed Energy Resources on the Reliability of a Critical Telecommunications Facility

    Energy Technology Data Exchange (ETDEWEB)

    Robinson, D.; Atcitty, C.; Zuffranieri, J.; Arent, D.

    2006-03-01

    Telecommunications has been identified by the Department of Homeland Security as a critical infrastructure to the United States. Failures in the power systems supporting major telecommunications service nodes are a main contributor to major telecommunications outages, as documented by analyses of Federal Communications Commission (FCC) outage reports by the National Reliability Steering Committee (under auspices of the Alliance for Telecommunications Industry Solutions). There are two major issues that are having increasing impact on the sensitivity of the power distribution to telecommunication facilities: deregulation of the power industry, and changing weather patterns. A logical approach to improve the robustness of telecommunication facilities would be to increase the depth and breadth of technologies available to restore power in the face of power outages. Distributed energy resources such as fuel cells and gas turbines could provide one more onsite electric power source to provide backup power, if batteries and diesel generators fail. But does the diversity in power sources actually increase the reliability of offered power to the office equipment, or does the complexity of installing and managing the extended power system induce more potential faults and higher failure rates? This report analyzes a system involving a telecommunications facility consisting of two switch-bays and a satellite reception system.

  19. A state-of-the art on decommissioning of nuclear facilities in Japan

    International Nuclear Information System (INIS)

    Park, Seung Kook; Kim, Hee Reyoung; Chung, Un Soo; Jung, Ki Jung

    2002-05-01

    While proceeding the KRR-1 and 2 decommissioning project, we are carried out study for the state of the art on decommissioning of nuclear facilities in Japan. Also, we are studied for the research reactors and commercial power plant that has the object of decommissioning, and for the government and the organization related on decommissioning operation. We are investigated for decommissioning activities of nuclear facilities achieved by JAERI, and collected the information and data for decommissioning techniques and computational system through the JPDR(Japan Power Demonstration Reactor) decommissioning activities. Such techniques are applying for Tokai Power Station began the decommissioning project from last year, and for Fugen Nuclear Power Station to be planned the decommissioning from 2003. Recent techniques for decommissioning was acquired by direct contact. The status of the treatment for decommissioning waste and the disposal facility for the very low-level radioactive concrete wastes was grasped

  20. Research Facilities for the Future of Nuclear Energy

    International Nuclear Information System (INIS)

    Ait Abderrahim, H.

    1996-01-01

    The proceedings of the ENS Class 1 Topical Meeting on Research facilities for the Future of Nuclear Energy include contributions on large research facilities, designed for tests in the field of nuclear energy production. In particular, issues related to facilities supporting research and development programmes in connection to the operation of nuclear power plants as well as the development of new concepts in material testing, nuclear data measurement, code validation, fuel cycle, reprocessing, and waste disposal are discussed. The proceedings contain 63 papers

  1. TMX, a new facility

    International Nuclear Information System (INIS)

    Thomas, S.R. Jr.

    1977-01-01

    As a mirror fusion facility, the Tandem Mirror Experiment (TMX) at the Lawrence Livermore Laboratory (LLL) is both new and different. It utilizes over 23,000 ft 2 of work area in three buildings and consumes over 14 kWh of energy with each shot. As a systems design, the facility is broken into discreet functional regions. Among them are a mechanical vacuum pumping system, a liquid-nitrogen system, neutral-beam and magnet power supplies, tiered structures to support these supplies, a neutron-shielded vacuum vessel, a control area, and a diagnostics area. Constraints of space, time, and cost have all affected the design

  2. Analysis of factors related to man-induced hazard for nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Young Soon; Jung, Jea Hee; Lee, Keun O; Son, Ki Sang; Wang, Sang Chul; Lee, Chang Jin; Ku, Min Ho; Park, Nam Young

    2003-03-01

    This study is to show a guide for installing hazardous facilities adjoined atomic power plant after finding out how much these facilities could impact to the atomic plant. Nuclear power plant is an important facility which is closely connected with public life, industrial activity, and the conduct of public business, so it should not be damaged. Therefore, if there are hazardous and harmful facilities near the plant, then they must be evaluated by the size, the type, and the shape. First of all, any factors that could cause man induced accident must be investigated. And they must be exactly evaluated from how much it will damage the plant facilities. The purpose of this study is to set a technical standard for the installation of these facilities by evaluating the man induced accident. Also, it is to make out the evaluation methods by investigating the hazardous facilities which are placed near the plant. Our country is now using CFR standard : reg. guide and IAEA safety series. However, not only the standard of technology which is related to man induced accident but also the evaluation methods for facilities are not yet layed down. As It was mentioned above, we should evaluate these facilities adequately, and these methods must be made out

  3. Analysis of factors related to man-induced hazard for nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young Soon; Jung, Jea Hee; Lee, Keun O; Son, Ki Sang; Wang, Sang Chul; Lee, Chang Jin; Ku, Min Ho; Park, Nam Young [Seoul National Univ. of Technology, Seoul (Korea, Republic of)

    2003-03-15

    This study is to show a guide for installing hazardous facilities adjoined atomic power plant after finding out how much these facilities could impact to the atomic plant. Nuclear power plant is an important facility which is closely connected with public life, industrial activity, and the conduct of public business, so it should not be damaged. Therefore, if there are hazardous and harmful facilities near the plant, then they must be evaluated by the size, the type, and the shape. First of all, any factors that could cause man induced accident must be investigated. And they must be exactly evaluated from how much it will damage the plant facilities. The purpose of this study is to set a technical standard for the installation of these facilities by evaluating the man induced accident. Also, it is to make out the evaluation methods by investigating the hazardous facilities which are placed near the plant. Our country is now using CFR standard : reg. guide and IAEA safety series. However, not only the standard of technology which is related to man induced accident but also the evaluation methods for facilities are not yet layed down. As It was mentioned above, we should evaluate these facilities adequately, and these methods must be made out.

  4. Regulations on the allocating of subsidies to promote the development of radiation exposure reduction technology for nuclear power facilities

    International Nuclear Information System (INIS)

    1984-01-01

    The regulations provide for subsidies for the research and development of radiation exposure reduction technology for nuclear power facilities and evaluation of the results. The subsidies are for purchase of equipment, materials, etc. and other expendures approved. The contents are as follows: applications for subsidies, determination of subsidy allocations, withdrawal of applications, a report on the work proceedings, a report on the results, confirmation on the sum of the subsidies, payment of subsidies, approval of alterations in the plans, withdrawal of the decision for subsidies, patent rights, payment of the earnings, management of the properties, etc. (Mori, K.)

  5. An optimization-based approach for facility energy management with uncertainties, and, Power portfolio optimization in deregulated electricity markets with risk management

    Science.gov (United States)

    Xu, Jun

    Topic 1. An Optimization-Based Approach for Facility Energy Management with Uncertainties. Effective energy management for facilities is becoming increasingly important in view of the rising energy costs, the government mandate on the reduction of energy consumption, and the human comfort requirements. This part of dissertation presents a daily energy management formulation and the corresponding solution methodology for HVAC systems. The problem is to minimize the energy and demand costs through the control of HVAC units while satisfying human comfort, system dynamics, load limit constraints, and other requirements. The problem is difficult in view of the fact that the system is nonlinear, time-varying, building-dependent, and uncertain; and that the direct control of a large number of HVAC components is difficult. In this work, HVAC setpoints are the control variables developed on top of a Direct Digital Control (DDC) system. A method that combines Lagrangian relaxation, neural networks, stochastic dynamic programming, and heuristics is developed to predict the system dynamics and uncontrollable load, and to optimize the setpoints. Numerical testing and prototype implementation results show that our method can effectively reduce total costs, manage uncertainties, and shed the load, is computationally efficient. Furthermore, it is significantly better than existing methods. Topic 2. Power Portfolio Optimization in Deregulated Electricity Markets with Risk Management. In a deregulated electric power system, multiple markets of different time scales exist with various power supply instruments. A load serving entity (LSE) has multiple choices from these instruments to meet its load obligations. In view of the large amount of power involved, the complex market structure, risks in such volatile markets, stringent constraints to be satisfied, and the long time horizon, a power portfolio optimization problem is of critical importance but difficulty for an LSE to serve the

  6. Modern tornado design of nuclear and other potentially hazardous facilities

    International Nuclear Information System (INIS)

    Stevenson, J.D.; Zhao, Y.

    1996-01-01

    Tornado wind loads and other tornado phenomena, including tornado missiles and differential pressure effects, have not usually been considered in the design of conventional industrial, commercial, or residential facilities in the United States; however, tornado resistance has often become a design requirement for certain hazardous facilities, such as large nuclear power plants and nuclear materials and waste storage facilities, as well as large liquefied natural gas storage facilities. This article provides a review of current procedures for the design of hazardous industrial facilities to resist tornado effects. 23 refs., 19 figs., 13 tabs

  7. A successful case site selection for low-and intermediate-level radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Lee, Bongwoo

    2007-01-01

    Korea decided on Gyeongju-si as the site of low-and intermediate-level radioactive waste disposal facility by referendum in November, 2005. Five success factors are considered; 1) the mayor and municipal assembly leaded the public opinion of inhabitants, 2) an invitation group was formed by citizen, social and religious group, 3) Gyeongju-si has operated the nuclear power plant since 20 years ago, and this radioactive waste disposal facility brings large financial support, 4) many kinds of public information means were used for invitation agreement and 5) the preconception, a nuclear facility is danger, was removed by visiting citizen, social group and local inhabitants at the nuclear power plant facility. Promotion process of the project, invitation process of Gyeongju-si and success factors, construction of an invitation promotion group and development of public information activities, publicity of financial effects and safety of radioactive waste disposal facility, increase of general acceptance among inhabitants by many kinds of public information means, and P.R. of safety of nuclear power plant facility by visiting leadership layers are reported. (S.Y.)

  8. Solar thermal power: the seamless solar link to the conventional power world

    International Nuclear Information System (INIS)

    Geyer, Michael; Quaschning, Volker

    2000-01-01

    This article focuses on solar thermal power generation and describes two solar thermal power concepts, namely, the parabolic trough or solar farm, and the solar central receiver or power tower. Details are given of grid-connected parabolic trough power plants in California and recent developments in collector design and absorber tubes, and the operation of power tower plants with different heat transfer media. Market issues are discussed, and solar thermal power projects under development, and application for support for solar thermal power projects under the Global Environment Facility's Operational Programme by Egypt, India, Iran, Mexico and Morocco are reported

  9. The text of the agreement between the Agency and Argentina for the application of safeguards to Embalse Power Reactor Facility

    International Nuclear Information System (INIS)

    1995-01-01

    The Agreement between the Republic of Argentina, the Federative Republic of Brazil, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials and the International Atomic Energy Agency for the Application of Safeguards came into force on 4 March 1994. As a result of the coming into force of the aforesaid Agreement for Argentina, the application of safeguards under the Agreement of 6 December 1974 between the Agency and the Government of the Republic of Argentina for the Application of Safeguards to the Embalse Power Reactor Facility has been suspended

  10. Progress in preliminary studies at Ottana Solar Facility

    Science.gov (United States)

    Demontis, V.; Camerada, M.; Cau, G.; Cocco, D.; Damiano, A.; Melis, T.; Musio, M.

    2016-05-01

    The fast increasing share of distributed generation from non-programmable renewable energy sources, such as the strong penetration of photovoltaic technology in the distribution networks, has generated several problems for the management and security of the whole power grid. In order to meet the challenge of a significant share of solar energy in the electricity mix, several actions aimed at increasing the grid flexibility and its hosting capacity, as well as at improving the generation programmability, need to be investigated. This paper focuses on the ongoing preliminary studies at the Ottana Solar Facility, a new experimental power plant located in Sardinia (Italy) currently under construction, which will offer the possibility to progress in the study of solar plants integration in the power grid. The facility integrates a concentrating solar power (CSP) plant, including a thermal energy storage system and an organic Rankine cycle (ORC) unit, with a concentrating photovoltaic (CPV) plant and an electrical energy storage system. The facility has the main goal to assess in real operating conditions the small scale concentrating solar power technology and to study the integration of the two technologies and the storage systems to produce programmable and controllable power profiles. A model for the CSP plant yield was developed to assess different operational strategies that significantly influence the plant yearly yield and its global economic effectiveness. In particular, precise assumptions for the ORC module start-up operation behavior, based on discussions with the manufacturers and technical datasheets, will be described. Finally, the results of the analysis of the: "solar driven", "weather forecasts" and "combined storage state of charge (SOC)/ weather forecasts" operational strategies will be presented.

  11. High intensity neutrino oscillation facilities in Europe

    Directory of Open Access Journals (Sweden)

    T. R. Edgecock

    2013-02-01

    Full Text Available The EUROnu project has studied three possible options for future, high intensity neutrino oscillation facilities in Europe. The first is a Super Beam, in which the neutrinos come from the decay of pions created by bombarding targets with a 4 MW proton beam from the CERN High Power Superconducting Proton Linac. The far detector for this facility is the 500 kt MEMPHYS water Cherenkov, located in the Fréjus tunnel. The second facility is the Neutrino Factory, in which the neutrinos come from the decay of μ^{+} and μ^{-} beams in a storage ring. The far detector in this case is a 100 kt magnetized iron neutrino detector at a baseline of 2000 km. The third option is a Beta Beam, in which the neutrinos come from the decay of beta emitting isotopes, in particular ^{6}He and ^{18}Ne, also stored in a ring. The far detector is also the MEMPHYS detector in the Fréjus tunnel. EUROnu has undertaken conceptual designs of these facilities and studied the performance of the detectors. Based on this, it has determined the physics reach of each facility, in particular for the measurement of CP violation in the lepton sector, and estimated the cost of construction. These have demonstrated that the best facility to build is the Neutrino Factory. However, if a powerful proton driver is constructed for another purpose or if the MEMPHYS detector is built for astroparticle physics, the Super Beam also becomes very attractive.

  12. A power measuring device

    International Nuclear Information System (INIS)

    As, R. van.

    1985-01-01

    As a part of the klystron test facility of the Dutch NIKHEF-K accelerator, a sensitive power measuring device has been built. The high-frequency power of a klystron is stored in a water-cooled dummy load. Using a microcomputer, the increase of the water temperature and the water flow rate are transformed to a digital indication of the klystron power. (Auth.)

  13. Seismic evaluation of existing nuclear power plants and other facilities V. 1. Proceedings of the technical committee meeting. Working material

    International Nuclear Information System (INIS)

    2002-01-01

    The objectives of this Tcm are: to review the IAEA Safety Report on Seismic Evaluation of Existing Nuclear Power Plants in order to achieve a consensus among Member States on this matter and to discuss the outlines of an IAEA Co-ordinated Research Programme on specific topics related to this subject. Today the nuclear industry relies much more on existing facilities than on the design of new ones. Nevertheless it appears that safety evaluation against external hazards is not a decreasing activity. The reason being that maintaining an acceptable level of nuclear safety requires periodic re-assessments of facilities, either because of modifications of the environment due to human activity or because of new data or new approaches in the assessment of natural hazards. In this regard, seismic re-evaluation has increasingly become a key issue for several existing nuclear facilities, including not only nuclear power plants but also other plants of the fuel cycle, as well as research reactors or laboratories. The IAEA has already supported development of engineering practices in this field by managing a Co-ordinated Research Programme, launched in 1992, on a Benchmark Study for the seismic analysis and testing of WWER 1000 type NPPs. It is now proposed to investigate other aspects of this issue. Many of these facilities were built according to older standards which did not take into account seismic hazard. Consequently, the seismic re-evaluation of existing facilities is a real challenge for earthquake engineers. In most of the cases, it is impossible to re-evaluate according to the up to date standards because entering these standards implies that some design rules are met, what is generally not the case for older facilities. In the best cases some rules exist for non nuclear buildings. In order to achieve a consensus on this matter, the IAEA intends to edit a Safety Report on 'Seismic Evaluation of existing NPPs'. The TCM will offer the opportunity to review the draft of

  14. Results from the CLIC Test Facility

    CERN Document Server

    Braun, H; Bossart, Rudolf; Chautard, F; Corsini, R; Delahaye, J P; Godot, J C; Hutchins, S; Kamber, I; Madsen, J H B; Rinolfi, Louis; Rossat, G; Schreiber, S; Suberlucq, Guy; Thorndahl, L; Wilson, Ian H; Wuensch, Walter

    1996-01-01

    In order to study the principle of the Compact Linear Collider (CLIC) based on the Two Beam Acceleration (TBA) scheme at high frequency, a CLIC Test Facility (CTF) has been set-up at CERN. After four years of successful running, the experimental programme is now fully completed and all its objectives reached, particularly the generation of a high intensity drive beam with short bunches by a photo-injector, the production of 30 GHz RF power and the acceleration of a probe beam by 30 GHz structures. A summary of the CTF results and their impact on linear collider design is given. This covers 30 GHz high power testing, study of intense, short single bunches; as well as RF-Gun, photocathode and beam diagnostic developments. A second phase of the test facility (CTF2) is presently being installed to demonstrate the feasibility of the TBA scheme by constructing a fully engineered, 10 m long, test section very similar to the CLIC drive and main linacs, producing up to 480 MW of peak RF power at 30 GHz and acceleratin...

  15. Analysis of the Opportunity for an Increase in the Thermal Power of Power Generating Units of Nuclear Power Plants (Part 1)

    OpenAIRE

    Chernousenko, Olga Yuriivna; Nikulenkova, Tetiana Volodymyrivna; Nikulenkov, Anatolii Hennadiiovych

    2017-01-01

    For Ukraine the realization of available reserves to increase the power of operating power units of nuclear plants is a vital problem the solution of which would allow us to increase electric power output. A special role is also played by economic priorities; in particular an increase in power by 1 kW is ten times cheaper in comparison with the construction of 1 kW of new power facilities. One more factor is the world experience in the field of an increase in the thermal power of operating po...

  16. Construction method for plant facility

    International Nuclear Information System (INIS)

    Ito, Arata; Hirono, Hideharu; Kyoda, Shigeru; Hanawa, Minoru; Sato, Hitoshi

    1998-01-01

    A caisson structure is disposed on a construction site for facilities of nuclear power plants. A digging work is performed below the caisson structure and, simultaneous with the digging work, a construction of a base, construction of plant facilities including a building and installation of plant facility are performed on the caisson structure. Then, the caisson structure is sank together with the structures on a base rock in association with the progress of the digging work and secured on the base rock. When securing them on the base rock, a groove is formed to the base rock along tuyere of the caisson structure so that the tuyere and a ceiling portion of the caisson structure are in direct contact with the base rock. Since the construction for the containing building conducted on the caisson structure is performed simultaneous with the digging work conducted below the caisson structure, the term required for the construction of the plant facilities can greatly reduced. (N.H.)

  17. External events analysis for experimental fusion facilities

    International Nuclear Information System (INIS)

    Cadwallader, L.C.

    1990-01-01

    External events are those off-normal events that threaten facilities either from outside or inside the building. These events, such as floods, fires, and earthquakes, are among the leading risk contributors for fission power plants, and the nature of fusion facilities indicates that they may also lead fusion risk. This paper gives overviews of analysis methods, references good analysis guidance documents, and gives design tips for mitigating the effects of floods and fires, seismic events, and aircraft impacts. Implications for future fusion facility siting are also discussed. Sites similar to fission plant sites are recommended. 46 refs

  18. Preliminary design of a Tandem-Mirror-Next-Step facility

    International Nuclear Information System (INIS)

    Damm, C.C.; Doggett, J.N.; Bulmer, R.H.

    1980-01-01

    The Tandem-Mirror-Next-Step (TMNS) facility is designed to demonstrate the engineering feasibility of a tandem-mirror reactor. The facility is based on a deuterium-tritium (D-T) burning, tandem-mirror device with a fusion power output of 245 MW. The fusion power density in the central cell is 2.1 MW/m 3 , with a resultant neutron wall loading of 0.5 MW/m 2 . Overall machine length is 116 m, and the effective central-cell length is 50.9 m. The magnet system includes end cells with yin-yang magnets to provide magnetohydrodynamic (MHD) stability and thermal-barrier cells to help achieve a plasma Q of 4.7 (where Q = fusion power/injected power). Neutral beams at energies up to 200 keV are used for plasma heating, fueling, and barrier pumping. Electron cyclotron resonant heating at 50 and 100 GHz is used to control the electron temperature in the barriers. Based on the resulting engineering design, the overall cost of the facility is estimated to be just under $1 billion. Unresolved physics issues include central-cell β-limits against MHD ballooning modes (the assumed reference value of β exceeds the current theory-derived limit), and the removal of thermalized α-particles from the plasma

  19. Engineering and technology in the deconstruction of nuclear materials production facilities

    International Nuclear Information System (INIS)

    Kingsley, R.S.; Reynolds, W.E.; Heffner, D.C.

    1996-01-01

    Technology and equipment exist to support nuclear facility deactivation, decontamination, and decommissioning. In reality, this statement is not surprising because the nuclear industry has been decontaminating and decommissioning production plants for decades as new generations of production technology were introduced. Since the 1950s, the Babcock and Wilcox Company (B ampersand W) has operated a number of nuclear materials processing facilities to manufacture nuclear fuel for the commercial power industry and the U.S. Navy. These manufacturing facilities included a mixed oxide (PuO 2 -UO 2 ) nuclear fuel manufacturing plant, low- and high-enriched uranium (HEU/LEU) chemical and fuel plants, and fuel assembly plants. In addition, B ampersand W designed and build a major nuclear research center in Lynchburg, Virginia, to support these nuclear fuel manufacturing activities and to conduct nuclear power research. These nuclear research facilities included two research reactors, a hot-cell complex for nuclear materials research, four critical experiment facilities, and a plutonium fuels research and development facility. This article describes the B ampersand W deactivation, decomtanimation, and decommisioning program

  20. Functional criteria for emergency response facilities. Technical report (final)

    International Nuclear Information System (INIS)

    1981-02-01

    This report describes the facilities and systems to be used by nuclear power plant licensees to improve responses to emergency situations. The facilities include the Technical Support Center (TSC), Onsite Operational Support Center (OSC), and Nearsite Emergency Operations Facility (EOF), as well as a brief discussion of the emergency response function of the control room. The data systems described are the Safety Parameter Display System (SPDS) and Nuclear Data Link (NDL). Together, these facilities and systems make up the total Emergency Response Facilities (ERFs). Licensees should follow the guidance provided both in this report and in NUREG-0654 (FEMA-REP-1), Revision 1, for design and implementation of the ERFs

  1. Nuclear power economic database

    International Nuclear Information System (INIS)

    Ding Xiaoming; Li Lin; Zhao Shiping

    1996-01-01

    Nuclear power economic database (NPEDB), based on ORACLE V6.0, consists of three parts, i.e., economic data base of nuclear power station, economic data base of nuclear fuel cycle and economic database of nuclear power planning and nuclear environment. Economic database of nuclear power station includes data of general economics, technique, capital cost and benefit, etc. Economic database of nuclear fuel cycle includes data of technique and nuclear fuel price. Economic database of nuclear power planning and nuclear environment includes data of energy history, forecast, energy balance, electric power and energy facilities

  2. Experimental measurements at the MASURCA facility

    International Nuclear Information System (INIS)

    Assal, W.; Bosq, J.C.; Mellier, F.

    2012-01-01

    Dedicated to the neutronics studies of fast and semi-fast reactor lattices, MASURCA (meaning 'mock-up facility for fast breeder reactor studies at Cadarache') is an airflow cooled fast reactor operating at a maximum power of 5 kW playing an important role in the CEA research activities. At this facility, a lot of neutron integral experimental programs were undertaken. The purpose of this poster is to show a panorama of the facility from this experimental measurement point of view. A hint at the forthcoming refurbishment will be included. These programs include various experimental measurements (reactivity, distributions of fluxes, reaction rates), performed essentially with fission chambers, in accordance with different methods (noise methods, radial or axial traverses, rod drops) and involving several devices systems (monitors, fission chambers, amplifiers, power supplies, data acquisition systems). For this purpose are implemented electronics modules to shape the signals sent from the detectors in various mode (fluctuation, pulse, current). All the electric and electronic devices needed for these measurements and the relating wiring will be fully explained through comprehensive layouts. Data acquired during counting performed at the time of startup phase or rod drops are analyzed by the mean of a Neutronic Measurement Treatment (TMN in French) programmed on the basis of the MATLAB software. This toolbox gives the opportunity of data files management, reactivity valuation from neutronics measurements and transient or divergence simulation at zero power. Particular TMN using at MASURCA will be presented. (authors)

  3. Experimental Measurements at the MASURCA Facility

    Science.gov (United States)

    Assal, W.; Bosq, J. C.; Mellier, F.

    2012-12-01

    Dedicated to the neutronics studies of fast and semi-fast reactor lattices, MASURCA (meaning “mock-up facility for fast breeder reactor studies at CADARACHE”) is an airflow cooled fast reactor operating at a maximum power of 5 kW playing an important role in the CEA research activities. At this facility, a lot of neutron integral experimental programs were undertaken. The purpose of this poster is to show a panorama of the facility from this experimental measurement point of view. A hint at the forthcoming refurbishment will be included. These programs include various experimental measurements (reactivity, distributions of fluxes, reaction rates), performed essentially with fission chambers, in accordance with different methods (noise methods, radial or axial traverses, rod drops) and involving several devices systems (monitors, fission chambers, amplifiers, power supplies, data acquisition systems ...). For this purpose are implemented electronics modules to shape the signals sent from the detectors in various mode (fluctuation, pulse, current). All the electric and electronic devices needed for these measurements and the relating wiring will be fully explained through comprehensive layouts. Data acquired during counting performed at the time of startup phase or rod drops are analyzed by the mean of a Neutronic Measurement Treatment (TMN in French) programmed on the basis of the MATLAB software. This toolbox gives the opportunity of data files management, reactivity valuation from neutronics measurements and transient or divergence simulation at zero power. Particular TMN using at MASURCA will be presented.

  4. Experimental measurements at the Masurca facility

    International Nuclear Information System (INIS)

    AssaI, W.; Bosq, J. C.; Mellier, F.

    2009-01-01

    Dedicated to the neutronics studies of fast and semi-fast reactor lattices, Masurca (meaning 'mock-up facility for fast breeder reactor studies at Cadarache') is an airflow cooled fast reactor operating at a maximum power of 5 kW playing an important role in the CEA research activities. At this facility, a lot of neutron integral experimental programs were undertaken. The purpose of this poster is to show a panorama of the facility from this experimental measurement point of view. A hint at the forthcoming refurbishment will be included. These programs include various experimental measurements (reactivity, distributions of fluxes, reaction rates), performed essentially with fission chambers, in accordance with different methods (noise methods, radial or axial traverses, rod drops) and involving several devices systems (monitors, fission chambers, amplifiers, power supplies, data acquisition systems...). For this purpose electronics modules are implemented to shape the signals sent from the detectors in various mode (fluctuation, pulse, current). All the electrical and electronic devices needed for these measurements and the relating wiring will be fully explained through comprehensive layouts. Data acquired during counting performed at the time of startup phase or rod drops are analyzed by the mean of a Neutronic Measurement Treatment (TMN in French) programmed on the basis of the MATLAB software. This toolbox gives the opportunity of data files management, reactivity valuation from neutronics measurements and transient or divergence simulation at zero power. Particular TMN using at Masurca will be presented. (authors)

  5. A new cryogenic test facility for large superconducting devices at CERN

    CERN Document Server

    Perin, A; Serio, L; Stewart, L; Benda, V; Bremer, J; Pirotte, O

    2015-01-01

    To expand CERN testing capability to superconducting devices that cannot be installed in existing test facilities because of their size and/or mass, CERN is building a new cryogenic test facility for large and heavy devices. The first devices to be tested in the facility will be the S-FRS superconducting magnets for the FAIR project that is currently under construction at the GSI Research Center in Darmstadt, Germany. The facility will include a renovated cold box with 1.2 kW at 4.5 K equivalent power with its compression system, two independent 15 kW liquid nitrogen precooling and warm-up units, as well as a dedicated cryogenic distribution system providing cooling power to three independent test benches. The article presents the main input parameters and constraints used to define the cryogenic system and its infrastructure. The chosen layout and configuration of the facility is presented and the characteristics of the main components are described.

  6. Decommissioning of nuclear fuel cycle facilities. Safety guide

    International Nuclear Information System (INIS)

    2001-01-01

    The objective of this Safety Guide is to provide guidance to regulatory bodies and operating organizations on planning and provision for the safe management of the decommissioning of non-reactor nuclear fuel cycle facilities. While the basic safety considerations for the decommissioning of nuclear fuel cycle facilities are similar to those for nuclear power plants, there are important differences, notably in the design and operating parameters for the facilities, the type of radioactive material and the support systems available. It is the objective of this Safety Guide to provide guidance for the shutdown and eventual decommissioning of such facilities, their individual characteristics being taken into account

  7. CLIC Test Facility 3

    CERN Multimedia

    Kossyvakis, I; Faus-golfe, A

    2007-01-01

    The design of CLIC is based on a two-beam scheme, where short pulses of high power 30 GHz RF are extracted from a drive beam running parallel to the main beam. The 3rd generation CLIC Test Facility (CTF3) will demonstrate the generation of the drive beam with the appropriate time structure, the extraction of 30 GHz RF power from this beam, as well as acceleration of a probe beam with 30 GHz RF cavities. The project makes maximum use of existing equipment and infrastructure of the LPI complex, which became available after the closure of LEP.

  8. Performance test of uninterruptible power system of PIEF

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jong Chae; Kim, Eun Ka; Chun, Yong Bum; Park, Dea Gyu; Chu, Yong Sun; Bae, Sang Min; Koo, Dae Seo

    1998-02-01

    Because of the special features of post-irradiation examination (PIE) facility to handle very high radioactive materials like spent nuclear fuels, the electric system of the facility was designed and constructed according to a very strict requirement which is applied to nuclear power plant. A safety grade of Class 1E was adopted in the power utility system of PIEF to guarantee stable power supply to the facility without any expected interruption. In order cope with a emergency condition like a power interruption of KEPCO, a emergency power supplying system consisting of a diesel generator (3-phase, 6600/440, 1,000 kW) and uninterruptibel power supply (UPS) system was installed in PIEF. UPS power is connected to the radiation monitoring system and several other main safety devices to assure of normal operations of them for not less than 30 minutes. According to the recommendations and regulations in nuclear law, a monthly and yearly regular inspection for the UPS and emergency power supplying system are performed. In this report, a brief description to establish self-inspection technology and procedures for the above mentioned electric power supplying system at PIEF, including a principle of operation, inspection scheme, trouble shooting, and performance test techniques were made. (author). 8 refs., 3 tabs., 4 figs.

  9. High Power Fiber Laser Test Bed

    Data.gov (United States)

    Federal Laboratory Consortium — This facility, unique within DoD, power-combines numerous cutting-edge fiber-coupled laser diode modules (FCLDM) to integrate pumping of high power rare earth-doped...

  10. Characteristics of SUS-MI cables and it's application to wiring in nuclear power facilities

    International Nuclear Information System (INIS)

    Okuno, Michio; Sato, Toshio; Handa, Katsue; Ohya, Shingo; Ioroi, Masaya

    1984-01-01

    SUS-MI cables are the inorganic insulation cables using austenitic stainless steel SUS 321 as the sheath, oxygen-free copper as the conductor and high purity magnesium oxide as the insulatingmaterial. Because of the excellent characteristics of the composing materials, the properties withstanding radiation, fire and heat, and sodium of the cables are superior. In the nuclear power facilities being developed such as fast breeder reactors and nuclear fusion reactors, there is the environment the cables with organic materials as the components cannot meet. As the cables to be applied to such places, the SUS-MI cables are most suitable. In this report, the electric properties and the mechanical strength of the cables and the examples of practical use are described. The highest temperature of using the SUS-MI cables is 800 deg C. The form and the composing materials of the SUS-MI cables, the characteristics and the cable laying are reported. Ceramic connectors and heat-resistant wall penetration parts were developed. The characteristics of the cables for the preheaters of fast breeder reactors are compared. (Kako, I.)

  11. Fuel conditioning facility material accountancy

    International Nuclear Information System (INIS)

    Yacout, A.M.; Bucher, R.G.; Orechwa, Y.

    1995-01-01

    The operation of the Fuel conditioning Facility (FCF) is based on the electrometallurgical processing of spent metallic reactor fuel. It differs significantly, therefore, from traditional PUREX process facilities in both processing technology and safeguards implications. For example, the fissile material is processed in FCF only in batches and is transferred within the facility only as solid, well-characterized items; there are no liquid steams containing fissile material within the facility, nor entering or leaving the facility. The analysis of a single batch lends itself also to an analytical relationship between the safeguards criteria, such as alarm limit, detection probability, and maximum significant amount of fissile material, and the accounting system's performance, as it is reflected in the variance associated with the estimate of the inventory difference. This relation, together with the sensitivity of the inventory difference to the uncertainties in the measurements, allows a thorough evaluation of the power of the accounting system. The system for the accountancy of the fissile material in the FCF has two main components: a system to gather and store information during the operation of the facility, and a system to interpret this information with regard to meeting safeguards criteria. These are described and the precision of the inventory closure over one batch evaluated

  12. State of radioactive waste management is power reactor facilities and state of radiation exposure of workers who engaged in radiation works in fiscal 1993

    International Nuclear Information System (INIS)

    1994-01-01

    This report is the summary of the reports on radiation control and others submitted by those who installed practical power reactor facilities based on the relevant law in fiscal 1993. The amounts of release of radioactive gaseous and liquid wastes were sufficiently smaller than the target value of the yearly release control for attaining the target value of dose that the public around the facilities receive. As to the state of control of radioactive solid waste, the amount of drum generation tended to decrease year by year, and the cumulative amount to be preserved tended to level off. The dose equivalent that the individuals who engaged in radiation works received was smaller than the limit value in all nuclear power stations. The total dose equivalent for those workers in fiscal 1993 was 86.65 man Sv. Hereafter, the automation and remote operation of works, the water quality control for reducing crud and so on will be promoted to reduce radiation exposure. The reference data on the state of control of gaseous, liquid and solid wastes, and the state of control of radiation exposure of workers are attached. (K.I.)

  13. Impacts on power reactor health physics programs

    International Nuclear Information System (INIS)

    Meyer, B.A.

    1991-01-01

    The impacts on power reactor health physics programs form implementing the revised 10 CFR Part 20 will be extensive and costly. Every policy, program, procedure and training lesson plan involving health physics will require changes and the subsequent retraining of personnel. At each power reactor facility, hundreds of procedures and thousands of people will be affected by these changes. Every area of a power reactor health physics program will be affected. These areas include; ALARA, Respiratory Protection, Exposure Control, Job Coverage, Dosimetry, Radwaste, Effluent Accountability, Emergency Planning and Radiation Worker Training. This paper presents how power reactor facilities will go about making these changes and gives possible examples of some of these changes and their impact on each area of power reactor health physics program

  14. 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

  15. Plasma-Materials Interactions Test Facility

    International Nuclear Information System (INIS)

    Uckan, T.

    1986-11-01

    The Plasma-Materials Interactions Test Facility (PMITF), recently designed and constructed at Oak Ridge National Laboratory (ORNL), is an electron cyclotron resonance microwave plasma system with densities around 10 11 cm -3 and electron temperatures of 10-20 eV. The device consists of a mirror cell with high-field-side microwave injection and a heating power of up to 0.8 kW(cw) at 2.45 GHz. The facility will be used for studies of plasma-materials interactions and of particle physics in pump limiters and for development and testing of plasma edge diagnostics

  16. Laundry monitor for nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Ishibashi, Mitsuo (Toshiba Corp., Fuchu (Japan). Fuchu Works)

    1984-06-01

    A laundry monitor has been developed for the detection and cleansification of radiation contamination on the clothes, headgear, footgear, etc. of workers in nuclear facilities. With this monitor, measurement is made irrespective of the size and shape of the objects; a large-area plastic scintillation detector is incorporated; it has stable and highly sensitive characteristics, with the merits of swift measurement, economical operation and easy maintenance. Connected with a folding machine, automatic carrying and storing compartment through a conveyor, it is capable of saving energy and man power, contributing to scheduled operation, and improving the efficiency of the facilities.

  17. Laundry monitor for nuclear facilities

    International Nuclear Information System (INIS)

    Ishibashi, Mitsuo

    1984-01-01

    A laundry monitor has been developed for the detection and cleansification of radiation contamination on the clothes, headgear, footgear, etc. of workers in nuclear facilities. With this monitor, measurement is made irrespective of the size and shape of the objects ; a large-area plastic scintillation detector is incorporated ; it has stable and highly sensitive characteristics, with the merits of swift measurement, economical operation and easy maintenance. Connected with a folding machine, automatic carrying and storing compartment through a conveyor, it is capable of saving energy and man power, contributing to scheduled operation, and improving the efficiency of the facilities. (author)

  18. Secure and Reliable Wireless Communications for Geological Repositories and Nuclear Facilities

    International Nuclear Information System (INIS)

    Twogood, R.

    2015-01-01

    There is an important need to develop new generation robust RF communication systems to support wireless communications and instrumentation control in geological repositories and nuclear facilities, such as nuclear power plants. Often these facilities have large metallic structures with electromagnetic (EM) transients from plant equipment. The ambient EMI/RFI harsh environment is responsible for degrading radio link bandwidth. Current communication systems often employ physical cables that are not only expensive to install, but deteriorate over time and are vulnerable to failures. Furthermore, conventional high-power narrowband walkie-talkies sometimes upset other electronics. On the other hand, high-quality reliable wireless communications between operators and automated control systems are critical in these facilities, as wireless sensors become more and more prevalent in these operations. In an effort to develop novel wireless communications systems, Dirac Solutions Inc. (DSI) in collaboration with Lawrence Livermore National Laboratory (LLNL), has developed high-quality ultra-wideband (UWB) hand-held communications systems that have proven to have excellent performance in ships and tunnels. The short pulse UWB RF technology, with bandwidths of many hundreds of MHz's, are non-interfering due to low average power. Furthermore, the UWB link has been shown to be highly reliable in the presence of other interfering signals. The DSI UWB communications systems can be adapted for applications in tunnels and nuclear power facilities for voice, data, and instrumentation control. In this paper we show examples of voice communication in ships with UWB walkie-talkies. We have developed novel modulation and demodulation techniques for short pulse UWB communications. The design is a low-power one and in a compact form. The communication units can be produced inexpensively in large quantities. A major application of these units might be their use by IAEA inspectors and

  19. The text of the agreement between the Agency and Argentina for the application of safeguards to the Atucha power reactor facility

    International Nuclear Information System (INIS)

    1995-01-01

    The Agreement between the Republic of Argentina, the Federative Republic of Brazil, the Brazilian-Argentine Agency for Accounting and Control of Nuclear Materials and the International Atomic Energy Agency for the Application of Safeguards came into force on 4 March 1994. As a result of the coming into force of the aforesaid Agreement for Argentina, the application of safeguards under the Agreement of 3 October 1972 between Argentina and the IAEA for the application of safeguards to the Atucha Power Reactor Facility has been suspended

  20. 33 CFR 127.107 - Electrical power systems.

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Electrical power systems. 127.107... Waterfront Facilities Handling Liquefied Natural Gas § 127.107 Electrical power systems. (a) The electrical power system must have a power source and a separate emergency power source, so that failure of one...